ML20196F739

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Summary of 880209 Meeting W/Util in Rockville,Md Re Remaining Informational Need Associated W/Util Proposed Spent Fuel Expansion.List of Attendees,Transcript & Slides Encl
ML20196F739
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 02/16/1988
From: Rooney V
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20196F727 List:
References
NUDOCS 8803040171
Download: ML20196F739 (42)
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Text

{{#Wiki_filter:!~ p February 16, 1988 Docket No.: 50-271 LICENSEE: Vermont Yankee Nuclear Power Corporation (VYNPC) FACILITY: Vermont Yankee Nuclear Power Station

SUBJECT:

MEETING

SUMMARY

On Tuesday, February 9 at 10:00 a.m., the NRC staff met with representatives of VYNPC to discuss remaining informational needs associated with VYNPC's proposed spent fuel pool expansion. A transcript, copy of the VYNPC slides that were presented, ard an attendance roster of this meeting are enclosed. ' Original sigced by: Vernon L. Rooney, Senior Project Manager Project Directorate I-3 Division of Reactor Projects I/II

Enclosures:

As stated cc: See next page m 0FC :PDI.

DIR 3

U NAME :VRo y mw :RWes an DATE:02/fT88

02/d/8A OFFICIAL RECORD COPY 8803040171 880216 PDR ADOCK 05000271 T

PDR

a i 2/9/88 MEETING RETWEEN NRC AND VYNPC REGARDING SPENT FUEL POOL EXPANSION Name Orcanization Vern Rooney NRC/PDI-3 Dick Wessman NRC/PDI-3 John Ridgely NPC/RES/SAIB J. S Wermiel NRC/NRR/ DEST /SPLB David K. McElwee Vermont Yankee Don Reid Vermont Yankee John R. Hoffman Yankee Atomic Warren Murphy Vermont Yankee Robert Capstick Yankee Atomic John DeVincentis Yankee Atomic John A. Ritsher Ropes & Gray Chris H. Hansen Yankee Atomic Ashok Thadani NRC/NRR Gus Lainas NRC/NRR/ADRII Joe Rutberg NRC/0GC Angela Chu NRR/SPLB Jack Kudrick NRR/SPLB George B. Dean Mass. Atty. Gen. Robert M. Weisman NRC/0GC Ann P. Hodgdon NRC/0GC Phillip L. Paull Vernont Public Service Dept. ] i

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a FUEL POOL COOLING DESIGN REQUIREMENTS

1. FUEL POOL COOLING SEISMIC CATEGORY I & SC-3
2. COOLING WATER SEISMIC CATEGORY I & SC-3
3. SINGLE ACTIVE FAILURE PROOF LOSS OF ELEC PWR ADEQUATE COOLING
4. DETECTORS FOR LOSS OF FUNCTION
5. DESIGN FOR:

DETECTION & ISOLATION OF LEAKS FLOODING MISSILES (INTERNAL & EXTERNAL) INSERVICE TESTING ALARA FIRE PROTECTION l

/ HEAT LOAD COMPARIS_ON i: NRC VY _ DAYS HEAT _LDAD DAYS HEAT LOAD u6.25 10.17 MBTU/HR 6 10.35 MBTU/HR 6.92 9.91 7 9.93 7.92 9.58 8 9.59 8.92 9.31 9 9.32 9.92 9.09 10 9.1

RESPONSE TO NRC QUESTIONS VY SPENT FUEL POOL EXPANSION OPEN ISSUES: 1

  • 2.__ HEAT REMOVAL CAPABILITY ITEMS:

A. 1971 ANS DRAFT STANDARD USED B. 9.1 MBTU/HR USED AS HEAT LOAD C. FSAR LISTS 2.23 MBTU/HR i

RESPONSE

A. NOT USED FOR SFP DECAY HEAT: USED FOR REACTOR VESSEL DECAY HEAT B. CONSERVATIVE VALUE FOR A SPECIFIC SCENARIO C. DES!9N VALUE NOT ACTUAL PERFORMANCE CAPABILITIES D. VY IS SINGLE ACTIVE FAILURE PROOF (VY HEAT EXCHANGERS CAN BE CROSS CONNECTED) CONCLUSION: ITEMS A,B,C AND D FULLY ADDRESSED BY EXISTING SFP SYSTEM HEAT REMOVAL CAPABILITY. PROPOSED UPGRADE ALB0 FULLY ADDRFSSES ITEMS B,C AND D.

g \\ i*se 0yOEmyb _A y1 3 gt % u 1y ke 0 8 ~ \\ W D 0 6 w A H O 2 L P T 2 ^ AE o H "P Y R AC S E 0 D 4 sH D y2 N A A D P O 1 LF + F x O ER O ,k 02 H 1 P 1 O \\ 1 \\. e 0 0 0 0 0 o 0 s 7 5 4 3 2 1 s 1 1 1 1

tr a b5aa.

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s RESPONSE TO NRC QUESTIONS VY SPENT FUEL POOL EXPANSION OPEN ISSUES:

  • e.

SPENT FUEL POOL TEMPERATURE LIMIT ITEM: NO FUEL POOL TEMPERATURE MONITOR WITH SFPCS NOT OPERATING

RESPONSE

POOL TEMPERATURE MONITORING IS PROVIDED FOR ALL PLANT CONDITIONS AS DOCUMENTED IN VY LETTER 9-1-87 CONCLUSION: EXISTING VY POOL TEMPERATURE MONITORING SYSTEM ACCEPTABLE AND ADEQUATE. PROPOSED SYSTEM WILL ADDITIONALLY PROVIDE SFP TEMPERATURE MONITORING FOR ALL PLANT CONDITIONS.

s RESPONSE TO NRC QUESTIONS VY SPENT FUEL POOL EXPANSION OPEN ISSUES: l POOLC00!_INGFOLLOWINGSEISMICEVENTS

  • a.

ITEM: A. FIRE WATER SYSTEM CONNECTION TO SERVICE WATER NOT SEISMIC CAT.I B. ALT. COOLING CELL PIPING SEISMIC CAT.I NOT DEMONSTRATED l C. RHRSW TO RHR CROSS-CONNECT SEISMIC CAT.I l NOT DEMONSTRATED i l

RESPONSE

A. SWS PIPING IS SEISMIC CAT.I PER FSAR App.A THROUGH A NORMALLY CLOSED MANUAL FIRE WATER SYSTEM ISO. VALVE B. PIPING IS SEISMIC CAT.I PER FSAR App.A C. PIPING IS SEISMIC CAT.I PER FSAR App.A CONCLUSION: EXISTING Vf SW PIPING AND CROSS-CONNECTION ARE SEISMIC CATEGORY I. PROPOSED FPC SYSTEM UPGRADE WILL BE SEISMIC CATEGORY I.

1 RESPONSE TO NRC QUESTIONS VY SPENT FUEL POOL EXPANSION i I OPEN ISSUES:

  • s.

SUPPLEMENTAL COOLING ITEM: A. PROVIDE ADDITIONAL INFORMATION ON PARALLEL HEAT EXCHANGER OPERATION B. SWITCHING RHR BETWEEN TORUS COOLING AND SFP COOLING IS UNACCEPTABLE

RESPONSE

A. ADDITIONAL INFORMATION CAN BE PROVIDED B. SWITCHING RHR BACK AND FORTH FROM TORUS COOLING TO SFP COOLING IS WITHIN THE CAPABILITIES OF THE PLANT CONCLUSION: EXISTING VY SFP SUPPLEMENTAL COOLING SYSTEM IS ADEQUATE AND ACCEPTABLE. PROPOSED NEW SYSTEM ALSO FULLY ADDRESSES THESE ISSUES. e e i i

4 t HEAT LOAD C_O_ M P A R I S O N NRC VY _ DAYS HEAT LOAD DAYS HEAT LOAD 6.25 10.17 MBTU/HR 6 10,35 MBTU/HR 6.92 9.91 7 9.93 7.92 9.58 8 9.59 8.92 9.31 9 9.32 9.92 9.09 10 9.1

t RESPONSE TO NRC QUESTIONS W SPENT FUEL POOL EXPANSION OPEN ISSUES:

    • __ RADIOLOGICAL CONSEQUENCES OF BOILING ITEM:

A. PROVIDE ASSUMPTIONS FOR OFF-SITE DOSE B. PROVIDE ASSUMPTIONS FOR ON-SITE DOSE C. PROVIDE O'4-S I T E DOSE 1 I

RESPONSE

A. ASSUMPTIONS CAN BE PROVIDED B. ASSUMPTIONS CAN BE PROVIDED C. ON-SITE DOSE CAN BE PROVIDED CONCLUSION: 10CFR2O REQUIREMENTS MET DURING POOL BOILING FOR OFF-SITE AND ON-SITE DOSES. PROPOSED NEW SYSTEM WILL PRECLUDE POOL BOILING FOR ALL PLANT CONDITIONS. 1

6 4 MEETING SUPPARY DISTRIBUTION Docket File NRC Particpants NRC'820'6Eal:PD8s VRooney PDI-3 R/F-DWessman RWessman 4Ridgely OGC AThadani EJordan Glains.s JPartiow JRutberg ACRS (10) AChu HBClayton JKudrick RWeismen AHodgdon

a February 16, 1988 Docket No.: 50-271 LICENSEC: Vermont Yankee Nuclear Power Corporation (VYNPC) FACILITY: Vermont Yankee Nuclear Power Station

SUBJECT:

MEETING

SUMMARY

On Tuesday, February 9 at 10:00 a.m., the NRC staff met with representatives of VYNPC to discuss remaining informational needs associated with VYNPC's proposed spent fuel pool expansion. A transcript, copy of the VYNPC slides that were presented, ard an attendance roster of this meeting are enclosed. Origial signed by: Vernon L. Rooney, Senior Project Manager Project Directorate I-3 Division of Reactor Projects I/II

Enclosures:

As stated cc: See next page m DFC :PDI-

DIR NAME :VRo y mw :RWes an DATE:02/f/88
02/il/84 9

OFFICIAL RECORD COPY f

4 2/9/88 MEETING BETWEEN NRC AND VYNPC REGARDING SPENT FUEL POOL EXPANSION I Name Organization Vern Rooney NRC/PDI-3 Dick Wessman NRC/PDI-3 -John Ridgely NPC/RES/SAIB J. S Wermiel NRC/NRR/ DEST /SPLB David K.'McElwee Vermont Yankee Don Reid Vermont Yankee John R. Hoffman Yankee Atomic Warren Murphy Vermont Yankee Robert Capstick Yankee Atomic John DeVincentis Yankee Atomic John A. Ritsher Ropes & Gray Chris H. Hansen Yankee Atomic Ashok Thadani NRC/NRR Gus Lainas NRC/NRR/ADRII Joe Putberg NRC/0GC i Angela Chu NRR/SPLB Jack Kudrick NRR/SPLB George B. Dean Mass. Atty. Gen. Robert M. Weisman NRC/0GC Ann P. Hodgdon NRC/0GC Phillip L. Paull Vermont Public Service Dept. 1 t + i i i i l t

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't FUEL POOL COOLING DESIGN REQUIREMENTS I

1. FUEL POOL COOLING SEISMIC CATEGORY I & SC-3
2. COOLING WATER SEISMIC CATEGORY I & SC-3 i
3. SINGLE ACTIVE FAILURE PROOF LOSS OF ELEC PWR l

ADEQUATE COOLING

4. DETECTORS FOR LOSS OF FUNCTION s
5. DESIGN FOR:

DETECTION & ISOLATION OF LEAKS FLOODING MISSILES (INTERNAL & EXTERNAL) l INSERVICE TESTING ALARA FIREPROTECTION

e HEAT LOAD COMPARISOR NRC VY _ DAYS HEAT LOAD DAYS HEAT LDAD 6.25 10.17 MBTU/HR 6 10.35 MBTU/HR 6.92 9.91 7 9.93 7.92 9.58 8 9.59 8.92 9.31 9 9.32 i 9.92 9.09 10 9.1 l

b i RESPONSE TO NRC QUESTIONS VY SPENT FUEL POOL EXPANSION OPEN ISSUES:

  • 2 __ HEAT REMOVAL CAPABILITY ITEMS:

A. 1971 ANS DRAFT STANDARD USED B. 9.1 MBTU/HR USED AS HEAT LOAD C. FSAR LIGTS 2.23 MBTU/HR

RESPONSE

A. NOT USED FOR SFP DECAY HEAT USED FOR REACTOR VESSEL DECAY HEAT B. CONSERVATIVE VALUE FOR A SPECIFIC SCENARIO C. DESISM VALUE NOT ACTUAL PERFORMANCE CAPABILITIES D. VY IS SINGLE ACTIVE FAILURE PROOF (VY HEAT EXCHANGERS CAN BE CROSS CONNECTED) CONCLUSION: ITEMS A,B,C AND D FULLY ADDRESSED BY EXISTING SFP SYSTEM HEAT REMOVAL CAPABILITY. PROPOSED UPGRADE ALSO FULLY ADDRESSES ITEMS B,C AND D.

c. > s >

ATTACHMENT 3 CALCULATION wc-6vz PAGE2 0F J PAGE3f0F ~ e 26 o* 6 e o Z ~ O. 2 10 e o y e O 5 ac c' u.O hJ 2OO. o N 5 S /~ o Y y d 1 1 ~1 n O i o O g R e, t

Mnin34n,

RESPONSE TO NRC QUESTIONS 4 VY SPENT FUEL POOL EXPANSION OPEN ISSUES: SPENT FUEL POOL TEMPERATURE LIMIT

  • ar.

1 i ITEM: NO FUEL POOL TEMPERATURE MONITOR WITH SFPCS NOT OPERATING

RESPONSE

POOL TEMPERATURE MONITORING IS PROVIDED FOR ALL PLANT CONDITIONS AS DOCUMENTED IN VY LETTER 9-1-87 CONCLUSION: EXISTING VY POOL TEMPERATURE MONITORING SYSTEM ACCEPTABLE AND ADEQUATE. PROPOSED SYSTEM WILL ADDITIONALLY PROVIDE SFP TEMPERATURE MONITORING FOR ALL PLANT CONDITIONS.

I

RESPONSE TO NRC QUESTIONS VY SPENT FUEL POOL EXPANSION OPEN ISSUES: P_00L COOLING FOLLOWING SEISMIC EVENTS

  • s.

ITEM: A. FIRE WATER SYSTEM CONNECTION TO SERVICE WATER NOT SEISMIC CAT.I B. ALT. COOLING CELL PIPING SEISMIC CAT.I NOT DEMONSTRATED C. RHRSW TO RHR CROSS-CONNECT SEISMIC CAT.I NOT DEMONSTRATED l

RESPONSE

l A. SWS PIPING IS SEISMIC CAT.I PER FSAR App.A THROUGH A NORMALLY CLOSED MANUAL FIRE WATER SYSTEM ISO. VALVE B. PIPING IS SEISMIC CAT.I PER FSAR App.A I C. PIPING IS SEISMIC CAT.! PER FSAR App.A CONCLUSION: EXISTING VY'SW PIPING AND CROSS-CONNECTION ARE l SEISMIC CATEGORY I. PROPOSED FPC SYSTEM UPGRADE WILL BE SEISMIC CATEGORY I.

4 RESPONSE TO NRC QUESTIONS VY SPENT FUEL POOL EXPANSION OPEN ISSUES:

  • s.

SUPPLEMENTAL COOLING ITEM: A. PROVIDE ADDITIONAL INFORMATION ON PARALLEL HEAT EXCHANGER OPERATION B. SWITCHING RHR BETWEEN TORUS COOLING AND SFP COOLING IS UNACCEPTABLE

RESPONSE

A. ADDITIONAL INFORMATION CAN BE PROVIDED B. SWITCHING RHR BACK AND FORTH FROM TORUS COOLING TO SFP COOLING IS WITHIN THE CAPABILITIES OF THE PLANT i CONCLUSION: EXISTING VY SFP SUPPLEMENTAL COOLING SYSTEM IS ADEQUATE AND ACCEPTABLE. PROPOSED NEW SYSTEM ALSO FULLY ADDRESSES THESE ISSUES. l

e HEAT L_O A D C_O M P A R I S_O.N_ l NRC VY DAYS HEAT LDAD DAYS HEAT LOAD r 6.25 10.17 MBTU/HR 6 10.35 MBTU/HR 6.92 9.91 7 9.93 7.92 9.58 8 9.59 8.92 9.31 9 9.32 9.92 9.09 10 9.1 4 e

RESPONSE TO NRC QUESTIONS VY SPENT FUEL POOL EXPANSION OPEN ISSUES: .. RADIOLOGICAL CONSEQUENCES OF BOILING ! TEM: A. PROVIDE ASSUMPTIONS FOR OFF-SITE DOSE B. PROVIDE ASSUMPTIONS FOR ON-SITE DOSE C. PROVIDE ON-SITE DOSE

RESPONSE

A. ASSUMPTIONS CAN BE PROVIDED B. ASSUMPTIONS CAN BE PROVIDED C. ON-SITE DOSE CAN BE PROVIDED CONCLUSION: 10CFR20 REQUIREMENTS MET DURING POOL BOILING FOR OFF-SITE AND ON-SITE DOSES. PROPOSED NEW SYSTEM WILL PRECLUDE POOL BOILING FOR ALL PLANT CONDITIONS. e

,4; i MEETING

SUMMARY

'0ISTRIBUTION Docket File' NPC Particpants NRC 4 Lee *1* M 5 VRooney PDI.3 R/F DWessman RWessman JRidgely OGC AThadani EJordan Gl.ainas JPartlow JRutberg ACRS (10) AChu HBClayton JKudrick RWeisman AHodqdon J 'l i e s l e

t 4 February 16,1988-Docket No.: 50-271 9 LICENSEE: Vermont Yankee Nuclear Power Corporation (VYNPC) FACILITY: Vermont Yankee Nuclear Power Station

SUBJECT:

MEETING

SUMMARY

On Tuesday, February 9 at 10:00 a.m., the NRC staff met with representatives of VYNPC to discuss remaining informational needs associated with VYNPC's proposed spent fuel pool expansion. A transcript, copy of the VYNPC slides that were presented, ard an attendance coster of this meeting are enclosed. Original siged by: Vernon L. Rooney, Senior Project Manager Project Directorate I.3 Division of-Reactor Projects I/II

Enclosures:

As stated cc: See next page m 0FC :PDI.

DIR NAME :VRo y mw :RWes n

DATE:02/f/88

02/d/8R 9

OFFICIAL RECORD COPY

2/9/38 MEETING BETWEEN NRC AND VYNPC REGARDING SPENT FUEL POOL EXPANSION Name Organization Vern Rooney NRC/PDI-3 Dick Wessman NRC/ POI-3 John Ridgely NPC/RES/SAIB J. S Wermiel NRC/NRR/ DEST /SPLB David K. McElwee Vermont Yankee Don Reid Vermont Yankee John R. Hoffman Yankee Atomic Warren Murphy Vermont Yankee Robert Capstick Yankee Atomic John DeVincentis Yankee Atomic John A. Ritsber Ropes & Gray Chris H. Hansen Yankee Atomic Ashok Thadani NRC/NRR Gus Lainas NRC/NRR/ADRII Joe Rutberg NRC/0GC Angela Chu NRR/SPLB Jack Kudrick NRR/SPLB George B. Dean Mass. Atty. Gen. Robert M. Weisman NRC/0GC Ann P. Hodgdon NRC/0GC Phillip L. Paull Vermont Public Service Dept. i i

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L FUEL POOL COOLING DESIGN REQUIREMENTS

1. FUEL POOL COOLING SEISMIC CATEGORY I & SC-3
2. COOLING WATER SEISMIC CATEGORY I & SC-3
3. SINGLE ACTIVE FAILURE PROOF LOSS OF ELEC PWR ADEQUATE COOLING t
4. DETECTORS FOR LOSS OF FUNCTION 4
5. DESIGN FOR:

DETECTION & ISOLATION OF LEAKS r FLOODING 1 MISSILES (INTERNAL & EXTERNAL) l INSERVICE TESTING ALARA FIRE PROTECTION I a i ~

!iEAT L_OAD C O M P A R I S O_N_ NRC VY DAYS HEAT LDAD DAYS HEAT LOAD 6.25 10.17 MBTU/HR 6 10.35 MBTU/HR 6.92 9.91 7 9.93 7.92 9.58 8 9.59 8.92 9.31 9 9.32 9.92 9.09 10 9.1 f

RESPONSE TO E QUESTIONS VY SPENT FUEL POOL EXPANSION OPEN ISSUES:

  • 2,_ HEAT REMOVAL _ CAPABILITY ITEMS:

A. 1971 ANS DRAFT STANDARD USED B. 9.1 MBTU/HR USED AS HEAT LOAD C. FSAR LISTS 2.23 MBTU/HR

RESPONSE

A. NOT USED FOR SFP DECAY HEAT: USED FOR REACTOR VESSEL DECAY HEAT B. CONSERVATIVE VALUE FOR A SPECIFIC SCENARIO l C. DESIGN VALUE NOT ACTUAL PERFORMANCE CAPABILITIES D. VY IS SINGLE ACTIVE FAILURE PROOF I (VY HEAT EXCHANSERS CAN BE CROSS CONNECTED) l CONCLUSION: ITEMS A.3,C AND D FULLY ADDRESSED BY EX13 TING SFP SYSTEM HEAT REMOVAL CAPABILITY. PROPOSED UPGRADE AL50 FULLY ADDRESSES ITEMS B,C AND D.

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TlRC, i

_0 i 8 N N N GN ID 06 A N H O 2 L P T 2 AE 0 H N "P Y R AC S E 0 D 4 N N SH D Y2 A A D P O I LF + F N O ER \\ O 0 C, 3 2 H 3 1 P / I 1 O \\ ) >i O 4 0 0 0 0 0 4 3 2 3, 8 7 1 1 1 1 1 ary $

RESPONSE TO NRC QUESTIONS W SPENT FUEL POOL EXPANSION OPEN ISSUES:

  • a.

SPENT FUEL POOL TEMPERATURE LIMIT ITEM: NO FUEL POOL TEMPERATURE MONITOR WITH SFPCS NOT UPERATING

RESPONSE

POOL TEMPERATURE MONITORING IS PROVIDED FOR ALL PLANT CONDITIONS AS DOCUMENTED IN VY LETTER 9-1-87 CONCLUSION: EXISTING VY POOL TEMPERATURE MONITORING SYSTEM ACCEPTABLE AND ADEQUATE. PROPOSED SYSTEM WILL ADDITIONALLY PROVIDE SFP TEMPERATURE MONITORING FOR ALL PLANT CONDITIONS.

4 RESPONSE TO NRC QUESTIONS I VY SPENT FUEL POOL EXPANSION 4 1 OPEN ISSUES: 1 I .* a. POOL COOLING FOLLOWING SEISMIC EVENTS ITEM: A. FIRE WATER SYSTEM CONNECTION TO SERVICE WATER NOT SEISMIC CAT.I B. ALT. COOLING CELL PIPING SEISMIC CAT.I NOT DEMONSTRATED C. RHRSW TO RHR CROSS-CONNECT SEISMIC CAT.I NOT DEMONSTRATED

RESPONSE

j l A. SWS PIPING IS SEISMIC CAT.I PER FSAR App.A 1 THROUGH A NORMALLY CLOSED MANUAL FIRE WATER SYSTEM 150. VALVE B. PIPING IS SEISMIC CAT.I PER FSAR App.A C. PIPING IS SEISMIC CAT.! PER FSAR App.A CONCLUSION: EXISTING VT SW PIPING AND CROSS-CONNECTION ARE SEISMIC CATEGORY I. PROPOSED FPC SYSTEM UPGRADE WILL BE SEISMIC CATEGORY 1.

t 4 RESPONSE TO NRC QUESTIONS W SPENT FUEL POOL EXPANSION OPEN ISSUES: es. SUPPLEMENTA_L COOLING ITEM: A. PROVIDE ADDITIONAL INFORMATION ON PARALLEL HEAT EXCHANGER OPERATION B. SWITCHING RHR BETWEEN TORUS COOLING AND SFP COOLING IS UNACCEPTABLE

RESPONSE

A. ADDITIONAL INFORMATION CAN BE PROVIDED B. SWITCHING RHR BACK AND FORTH FROM TORUS COOLING TO SFP COOLING IS WITHIN THE CAPABILITIES OF THE PLANT CONCLUSION: EXISTINd VY SFP SUPPLEMENTAL COOLING SYSTEM IS ADEQUATE AND ACCEPTABLE. PROPOSED NEW SYSTEM ALSO FULLY ADDRESSES THESE ISSUES.

ELEAT L_0_A D C_OMPA_.RISON NRC VY DAYS HEAT LOAD DAYS HEAT LOAD 6.25 10.17 MBTU/HR 6 10.35 MBTU/HR 6.92 9.91 7 9.93 7.92 9.58 8 9.59 8.92 9.31 9 9.32 9.92 9.09 10 9.1

4 1 RESPONSE TO NRC QUEST 10NS VY SPENT FUEL POOL EXPANSION OPEN ISSUES: RADIOLOGICAL CONSE9UENCES OF BOILING

  • <+._

ITEM: A. PROVIDE ASSUMPTIONS FOR OFF-SITE DOSE B. PROVIDE ASSUMPTIONS FOR ON-SITE DOSE C. PROVIDE ON-SITE DOSE

RESPONSE

A. ASSUMPTIONS CAN BE PROVIDED B. ASSUMPTIONS CAN BE PROVIDED C. ON-SITE DOSE CAN BE PROVIDED CONCLUSION: 10CFREO REQUIREMENTS MET DURING POOL BOILING FOR OFF-SITE AND ON-SITE DOSES. PROPOSED NEW SYSTEM WILL PRECLUDE POOL BOILING FOR ALL PLANT CONDITIONS. e}}

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