ML17298B680
| ML17298B680 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/17/1984 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| ANPP-31493-EEVB, NUDOCS 8412200226 | |
| Download: ML17298B680 (14) | |
Text
REGULATORY FORMATION DISTRIBUTION SY M (BIDS)
ACCESSION'BR: 8412200226 DOC, DATE! 84/12/17 NOTARIZED:
YES FACIL:STN-50-528 Palo Verde Nuclear Station< Unit 1< Arizona Publi STN-50-529 Palo Verde Nuclear Station~
Unit 2< Arizona Publi STN-50-530 Palo Verde Nuclear Station~
Unit 3~ Arizona Publ-i AUTH'AME AUTHOR AFFILIATION VAN BRUNTiE ~ E.
Arizona Public Service Co, RECIP ~ NAME RECIPIENT AFFILIATION KNIGHTON<G.P( ~
Licensing Branch 3
SUBJECT:
Forwards draft proposed FSAR changes reflectinp requirements for condensate storage tank 8 atmospheric dupm valve nitrogen accumulator.Changes also reflect".util intent to verify boron mixing under natural circulation, DISTRIBUTION CODE:
B001D COPIES RECEIVED;LTR ENCL SIZE ~
TITLE: Licensing Submittal:
PSAR/FSAR Amdts L Related Correspondence NOTES:Standardized plant ~
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- plant, Standardized
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Arizona Public Service Company Director of Nuclear Reactor Regulation Mr. George W. Knighton, Chief Licensing Branch No.
3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 ANPP-31493-EEVB/WFQ December 17, 1984
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, and 3
Docket Nos.
STN 50-528/529/530 Natural Circulation Cooldown Testing File: 84-056-026'.1.01.10
References:
(A)
Letter from A. E. Scherer, C-E, to D. G. Eisenhut,
- NRC, dated August 12, 1983 (LD-83-074).
(B)
Letter from E. E.
Van Brunt, Jr.,
APS, to G.
W. Knighton, NRC, dated August 7, 1984 (ANPP-30141).
Dear Mr. Knighton:
As discussed with Mr. E. A. Licitra of your staff, attached are draft proposed FSAR changes for your information.
These changes are necessary to make FSAR Appendix 5A consistent with the analyses and commitments provided by references (A) and (B), respectively.
Specifically the draft proposed FSAR changes reflect the requirements for the Condensate Storage Tank and the Atmospheric Dump Valve Nitrogen Accumulator with regard to Branch Technical Position RSB 5-1.
The attached proposed changes also reflect APS'ntent to verify adequate boron mixing under natural circula-tion conditions.
Please contact Mr. W. F. Quinn of my staff if you have any questions on this matter.
Very truly yours, E.Q.. Ua 5~g~
E. E.
Van Brunt, Jr.
APS Vice President Nuclear Production ANPP Project Director EEVB/TFQ/mb Attachment E. A. Licitra R. P.
Zimmerman A. C. Gehr 8412~
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ANPP-31493 STATE OF ARIZONA
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I, A. Carter Rogers, represent that I am Manager, Nuclear Engineering of Arizona Public Service Company, that the foregoing document has been signed by me on behalf of Arizona Public Service Company with full authority to do so, that I have read such document and know its contents and that to the best of my knowledge and belief, the statements made therein are true.
A. Carter Rogers Sworn to before me this ~ldey 1984.
Not ry Public y
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My Commlssjotl Expires April 6, 1987 My Commis'sion Expires:
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INSERT A to Page 5A.14 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at hot standby plus 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of operation to reach cold shutdown under natural circulation conditions.
INSERT B to Page 5A-15 Testing will also be conducted to verify adequate boron mixing under natural circulation conditions and the ability to perform a natural, circulation cooldown agd a plant depressurization to shutdown cooling indicating conditions.<
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PVNGS FSAR APPENDIX 5A Question Question circulation conditions must be available to the operator.
Summarize these procedures.
Discuss the availability of the Seismic Category I auxiliary feedwater supply for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at hot shutdown plus cooldown to the RHR system cut-in based on longest time for the availability of only onsite or only offsite power and assuming a single failure. If this cannot be achieved, discuss the availability of an adequate alternate Seismic Category I water source.
5.
What provisions in natural circulation cool-down methods have been made to account for possible upper head void formation?
RESPONSE
The response will be provided on the CESSAR docket.
Additional clarification is provided as follows:
l.a.
PVNGS provides, as a backup to the instrument air
- system, safety grade nitrogen accumulators to operate the steam generator atmospheric dump
.valves (ADVs)
The accumulators provide nitroge supply for Mhours of operation of these valves.
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(a)~hid e A'ne nitrogen accumulator is provided for each ADV.
A single failure will not result in loss of capability to vent the minimum required amount of steam necessary for decay heat removal and plant cooldown.
1.b.
The response to NRC Question 440.9 discusses power lockout for the safety injection tank (SIT) vent a.
Re-evaluation of the Nitrogen Accumulators to the ADVs, will be performed when the C-E Owners Group effort on NUREG-0737, Item II.K.2.17, Potential for Voiding in the Reactor Coolant System during transients, is completed.
Amendment 7
'A-14 December 1981
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and isolation valves.
Additionally, power can be restored to the SIT vent valves from the control room to depressurize the SITs.
Each SIT can be isolated or vented'rom the control room.
There is no single failure which could result in the opening of all SIT isolation valves or could preclude RCS depressurization.
1.c.
As stated in section 9.3.4.1, the charging pumps are not automatically sequenced onto the emergency buses.
The charging pumps can be loaded onto the emergency buses from the control room.
RHR pressure relief discharge piping is provided with a sparger that, is located at the bottom of the containment emergency sump.
On that basis, no direct steam flow would be directed toward any personnel.
Cooldown under natural circulation conditions was analy-tically modeled and positively confirmed following two events at an operating C-E reactor plant.
St. Lucie Unit 1 (Docket No. 50-335) performed two natural circu-lation cooldowns following a reactor trip from full power conditions in 1977 and in 1980.
A test to verify natural circulation for System 80 is scheduled to be conducted as part of the power ascension testing.
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~~se87 B San Onofre Unit 2 is scheduled to conduct a boron mixing test during their upcoming power ascension testing.
Since the boron mixing in the RCS is accomplished in a similar environment and by the same process, the San Onofre natural circulation flow boron mixing test results are considered proto-typical for the System 80 standard design.
Following completion of the San Onofre test, the results will be assessed for the applicability to System 80.
Amendment 8
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PVNGS FSAR APPENDIX 5A Specific natural circulation and natural circulation cooldown operator guidelines have been prepared by C-E for the C-E Owners Group.
These guidelines were trans-mitted in CEN-152 to the NRC for review (June, 1981).
These guidelines provide instruction to avoid void formation in the reactor vessel upper head that could occur during natural circulation conditions.
Also included are instructions that deal with the symptoms and follow-up actions for a condensable reactor vessel void if one should occur.
The condensate storage tank (CST) is discussed in section 9.2.6.
The tank is designeg to provide suffici-ent auxiliary feedwater supply for4 hours at hot standby Cmetu4iag-ee~
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(b)
A single failure will not result in loss of water supply such that cooling to RHR initiation cannot be achieved.
- Pumps, valves, and piping required for essential operation are redundant, separated, and protected from adverse environmental effects.
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- b. LD~~ Letter from A E. Scberer g-E, to D. G. Eisenhut, NRC, dated,,
provided a A'aV1$4-O Report on Natural Circulation Cooldown of CE System 80 NSSS.
This report verifies the CST design is adequate.
Amendment 12 5A-15A February 1984
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