ML20212Q814

Forwards Applicant 860821 & 0902 Ltrs to NRC Re Board Notification 86-018,for Info.W/Svc List.Related Correspondence

ML20212Q814
Person / Time
Site:	Vogtle
Issue date:	09/03/1986
From:	Doris Lewis GEORGIA POWER CO., SHAW, PITTMAN, POTTS & TROWBRIDGE
To:	Linenberger G, Margulies M, Paris O Atomic Safety and Licensing Board Panel
References
CON-#386-603 OL, NUDOCS 8609080057
Download: ML20212Q814 (6)

Text

_____________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

[ 63 4euito 6 DOCKETED SHAW, PlTTMAN, PoTTs & TROWBRIDGE USNRC A #ARTNgnSMap OF pmOFESSIONAL CORPORATICMS i.oo - Sracer. ~. w.

7tLtx w ASHINGTON. o. C. 2oO36 W SEP -5TELECopitR A10:48 89 2693 (SHAwLAW WSH) (202) 822409e 4. 822-st99 CASLE SHAWLAW*

OFFICE OF Uds,An'isd TELEPMoNE 00CKElihG =C2i=2n sa (202) saa-sooo 3R / }h't!

wairtm's DantCT oiAL Nuustm 822-1474 September 3, 1986 Morton B. Margulies, Chairman Mr. Gustave A. Linenberger, Jr.

Administrative Law Judge Administrative Judge I Atomic Safety and Licensing Atomic Safety and Licensing ~

l Board Board U.S. Nuclear Regulatory U.S. Nuclear Regulatory Commission Commission Washington, D.C. 20555 Washington, D.C. 20555 Dr. Oscar H. Paris Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D.C. 20555 In the Matter of Georgia Power Company, et al.

(Vogtle Electric Generating Plant, Units 1 and 2 Docket Nos. 50-424 and 50-425 d4 Gentlemen:

In reference to Board Notification No. P6-18 (re ?.SCO valves), enclosed for the Board's information are copies of two letters (without attachments) from Applicants to the NRC Staff.

Sincerely, w

David R. Lewis Counsel for Applicants cc w/ enc 1:

Service List 8607090057 860903 PDR ADOCK 05000424 G PDR DSD3 _

rj e

,.. Geo'9'mco PoetO Scu 2s2a Pbwer Company Dw5.l?E24.

404 7244114 SouN CcmrefY Serwcas, Irc Post Office Bom 262f.

3rmingham. Alecame 352o2 h 205 874601t

. Vogtle Project August 21, 1986 Director of Nuclear Reactor Regulation Files X6BK15 Attention: Mr. B. J. Youngblood Log GN-1049 PWR Project Directorare #4 Division of PWR Licensing A U. S. Nuclear Regulatory Commission '

Washington, D.C. 20555 REF: BAILEY TO DENTON, GN-963, DATED 6/25/86 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PLANI - UNITS 1 AND 2 A SER CONFIRMATORY ITEM 9: STEAMLINE BREAK OUTSIDE CONTAINMENT

Dear Mr. Denton:

The following information, as discussed in a conference call with your staff on August 19, 1986, is provided to clarify the use of ASCO solenoid valves in the Main Steam Isolation Valve (MSIV) areas.

The VEGP design utilites four models of ASCO solenoid vsives in safety-related applications: NP8316', NP8320, NP8321, and 206-381.

One NP8316 is located in the MSIV area. It is associated with the containment isolation valve for the nitrogen supply to the safety injection accumulato:s and is not required to function for a Main Steam Line Break (MSLB) in the MSIV area.

Eighteen prccess valves utilize NP8320 solenoid valves. Six of the process valves (steam gecerator layup isolation valves (4) and electric steam boiler isolation valves (2)) are not essential for the MSLB in the MSIV area; the other 12 process valves (nain steam bypass valves (8) and feedwater control bypass valves (4)) are essential for a MSLB in the MSIV ares. The calculated temperature conditions exieting in the vicinity of the NP8320 solenoid valves do not exceed the qualification temperature of 420*F documented in ASCO Test '

Report No. AQR-67368 (Rev.1) and Westinghouse WCAP 8687 (Supp. 2 - H02A/H05A, Rev. 2).

C i

m__

c

\

e

- Director of Nuclear Reactor Regulation File X7BC35 August 20, 1986 Lcs: GN-1049 Page 2 Eight process valves utilize NP8321 solenoid valves. Four of these process valves are located in the Auxiliary Building where the ambient temperature does not exceed the qualification temperature of 346*F. For the four process -

valves in the Control Building, a thermal lag analysis using the methodology consistant with NUREG-0588, shows that the valve itself does not exceed its qualification temperature. In addition, these valves perform their essential function before the ambient temperature exceeds the qualification temperature of 346*F.

The 206-381 solenoids are not located in the MSIV area and perform no essential function for the MSLB in the MSIV area.

If your staff requires any additional information, please do not hesitate to contact me.

Since rely, '

h.

J. A. Bailey Project Licensing Manager C

JAB /se xet R. E. Conway -

R. A. Thomas J. E. Joiner, Esquire B. W. Churchill, Esquire M. A. Miller (2)

5. Jones, Esquire G. Bockhold, Jr.

NRC Regional Administrator NRC Resident Inspector D. C. Teper W. C. Ramsey L. T. Cucwa Vogtle Project File 06747

(,

' Georga Power Corroany Post Office Box 282

• Waynescoro, Georga 30830 Teleonor's 404 554 9961 EM 7244114 Southern Corroeny Serwces, fric.

Fest Office Ben 2625 Bir:rungearn.'A'abama 352C2 Vogtle Project September 2,1986 Director of Nuclear Reactor Regulation Files X6BK15 Attention: Mr. B. J. Youngblood Log: GN-1066 PWR Project Directorate #4 Division of PWR Licensing A U. S. Nuclear Regulaton Commission .

Washington, D.C. 20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PIANT - UNITS 1 AND 2 SER CONFIRMATORY ITEM 9: STEAM LINE BREAK OUTSIDE CONTAINMENT (PROPRIETARY)

Dear Mr. Denton:

This letter and attachments reconfirm the environmental qualification of ASCO solenoid valves for a main steam line break (MSLB) outside containment. The attachments document information that we discussed with your staff in meetings on August 27-28. It is our understanding that the information provided .

resolved the staff's questions as they pertained to ASCO salves.

i On June 25, 1986, Georgia Power Company submitted an analysis of steam line breaks o'itside containment in response to SER confirmatory ites 9. By letter dated August 12, 1986, your staff requested further information concerning a l thermal lag analysis performed by Westinghouse to environmentally qualify certain equipment (including certain ASCO solenoid valve) in main steam isolation valve (MSIV) areas against an MSLB.

As indicated in our letter dated August 21, 1986, one model of ASCO solenoid valve in MSIV areas -- the model NP8321 -- has been qualified by thermal lag analysis. The analysis was applied to four process valves (each of which contains two NP8321 valves) in the control Building. As discussed in the

'Jene 25, 1986 submittal, the thermal lag analysis was based on Bechtel's FLUD code, which determined Vogtle-specific MSLB steam conditions in the locations of the valves. This code, which is proprietary, is provided as Attachment 1.1 The thermal tag analysis demonstrated that the NP8321 valves, which are qualified to a temperature of 346'F, would reach a maximum l

2 This proprietary code is submitted under the provisions of 10 CFR $2.790(b). The affidavit required by that section is submitted as Attachment 2.

Director of Nuclear Reactor Regulation File: X6BK15 September 2,1986 Lost GN-1066 Page 2 temperature of 326'F. Other ASCO solenoid valves in MSIV areas are either not cubjcot to ambient temperatures in excess of their qualitication temperatures or are not required to function in the event of an MSLB.

In your staff's August 12 request for information, the staff raised six questions regarding the t.hermal lag analysis as it applied to equipment (not just ASCO valves) subject to a MSLB environment outside containment.

Questions 1-5 are inapplicable to Westinghouse's thermal lag analysis as applied to the ASCO valves. Questions 1-5 relate to assumptions used to determine a condensing heat transfer rate (for the transitory phase before saturation temperature is reached and convective heat transfer occurs), and to the time the equipment remains in a drying-out stage at saturation temperature. Westinghouse's thermal lag analysis, however, conservatively assumes that the ASCO valves in question start at saturation temperature and ^

are already dry. The analysis applies the forced convection heat transfer coefficient throughout the entire superheat transient. If Westinghouse hari chosen to model the condensing heat transfer phase and the drying-out phase, the calculated maximum valve temperature would have been about one degree lower.

Question 6 asked whether Westinghouse's thermal lag analysis conformed to NUREG-0588, Appendix B. As indicated above, Westinghouse conservatively chose to assume that the ASCO valves would instantaneously rise to saturation temperature and instantaneously dry out. Westinghouse then used the NUREG-0588 Appendix B equation to calculate the forced convection heat transfer coefficient and added an additional temperature increment (l'P) to account for the component surface temperature variation. For these reasons and as discussed more fully in Attachment 3, the Westinghouse analysis conservatively meets the requirements of NUREG-0588.

If your staff requires any additional information on the thermal lag analysis as applied to ASCO valves, please do not hesitate to contact me. Information pertaining to other types of equipment in MSIV areas will be submitted shortly.

Sincerely, J. A. Bailey Project Licensing Manager JAB /sm xc R. E. Conway NRC Regional Administrator R. A. Thomas NRC Resident Inspector

.J. E. Joine r, Esquire D. C. Teper B. W. Churchill, Esquire W. C. Ramsey M. A. Miller (2) L. T. Cucwa B. Jones, Esquire Vo8tle Project File G. Bockhold, Jr.

0700V

F

\

l.

I UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing Board In the Matter of )

)

GEORGIA POWER COMPANY, et al. ) Docket No. 50-424

) 50-425 (Vogtle Electric Generating Plant, )

Units 1 and 2) )

SERVICE LIST Morton B. Margulies, Chairman Atomic Safety and Licensing Atomic Safety and Licensing Board Board Panel U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Washington, D.C. 20555 Commission Washington, D.C. 20555 Mr. Gustave A. Linenberger Atomic Safety and Licensing Board Atomic Safety and Licensing U.S. Nuclear Regulatory Commission Appeal Board Panel Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Dr. Oscar H. Paris Washington, D.C. 20555 Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Douglas C. Teper Washington, D.C. 20555 1253 Lenox Circle Atlanta, Georgia 30306 Bernard M. Bordenick, Esq. .

Office of Executive Legal Director Bradley Jones, Esquire U.S. Nuclear Regulatory Commission Regional Counsel Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Docketing and Service Section Suite 3100 Office of the Secretary 101 Marietta Street U.S. Nuclear Regulatory Commission Atlanta, GA 30303 Washington, D.C.

20555

. . - - - - _ - _ - . . _ - .