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Questions Study

The document contains a list of technical and operational questions related to NPCIL, including details about manpower, reactor design criteria, and incidents involving Instrumented Relief Valves (IRV). It also addresses emergency cooling systems, fuel management, and future planning for NPCIL. The questions indicate a focus on safety, efficiency, and operational integrity in nuclear reactor management.

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vikasyadav100
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34 views1 page

Questions Study

The document contains a list of technical and operational questions related to NPCIL, including details about manpower, reactor design criteria, and incidents involving Instrumented Relief Valves (IRV). It also addresses emergency cooling systems, fuel management, and future planning for NPCIL. The questions indicate a focus on safety, efficiency, and operational integrity in nuclear reactor management.

Uploaded by

vikasyadav100
Copyright
© © All Rights Reserved
We take content rights seriously. If you suspect this is your content, claim it here.
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Download as DOCX, PDF, TXT or read online on Scribd
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Name – Abhishek Kumar Gupta

1- What is the current sanctioned strength of NPCIL-HQs?


2- What is the total manpower of NPCIL?
3- Comparison of MWe to manpower between NPCIL and NTPC.
4- Why is an IRV (Instrumented Relief Valve) required?
5- What provisions exist to avoid over-pressurization in LWR or VVER-type
reactors?
6- What are the design criteria of the IRV?
7- What are the boxed-up logic conditions for the BCD (Bleed Condenser)?
8- Why was the boxed-up logic at 30 Kg/cm² BCD pressure provided in 220 MWe
reactors? Was this part of the initial BCD design?
9- Explain the Narora (220 MWe) light water injection incident during IRV
failure/malfunction.
10- What changes were made in BCD outlet temperature boxed-up sensing after
the KAPS event? What was the reason?
11- What is the set point of the BCD Relief Valve (RV)?
12- Why are there two different set points for the same Relief Valve (RV)?
13- What is the major reason for IRV malfunction?
14- What corrective actions have been taken to prevent this in 220 MWe
reactors?
15- Have there been any changes in the IRV design for 700 MWe reactors?
16- What are the ECCS (Emergency Core Cooling System) design acceptance
criteria?
17- What is meant by “coolable geometry” of the core?
18-
19- What corrective action should be taken if the ECCS TK-2 purge valve starts
passing during ECCS testing?
20- What will happen if NRV-13 of the D2O injection line starts passing during
ECCS testing?
21- What will happen if passing (leakage) is very high?
22- Is the pipeline between NRV-13 and ECCS TK-1 qualified for PHT pressure and
temperature?
23- What is the RV set point of ECCS TK-2?
24- What is the discharge burnup of a VVER-type reactor, and what is its average
enrichment?
25- What is the average enrichment of spent fuel discharged from a VVER
reactor?
26- Can this spent fuel be used in PHWR-type reactors?
27- How can we manage the excess reactivity in the same design of a PHWR-type
reactor? (Use of Boron in Moderator or burnable poison in fuel)
28- Suppose we use 1% enriched fuel in a PHWR — what will be the expected
discharge burnup (13–14K MWD/Tn-U)?
29- Why are we achieving higher discharge burnup compared to LWR-type
reactors in terms of enrichment to discharge burnup?
30- In PHWR-type reactors, what is the contribution of plutonium (Pu) to the total
energy produced in an equilibrium core?
31- Some other questions were also asked from Recruitment, future target and
Succession planning of NPCIL from my recommendation.

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