ML18136A102

Summary of 790921 Meeting W/Util & S&W Re Auxiliary Feedwater Contribution to Energy in Containment Following Main Steamline Break

ML18136A102
Person / Time
Site:	Beaver Valley, Surry, North Anna
Issue date:	10/18/1979
From:	Wigginton D Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TAC-12263, NUDOCS 7910260136
Download: ML18136A102 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Docket Nos.: 50-33~

50-33~

and 50-334 OC I Oil ER t 8 19/9 LICENSEES:

Virginia* E.l ectri c and Power Company Duquesne Light Company FACILITIES:

Surry, Unit Nos. 1 & 2 North Anna, Unit Nos. l & 2 Beaver Valley, Unit No. l

//)-18119

SUMMARY

OF SEPTEMBER 21, 1979 MEETING ON AUXILIARY FEEDHATER CONTRIBUTION TO ENERGY IN CONTAINMENT FOLLOWING A MAIN STEAM LINE BREAK The licensees and Stone and Webster met with the staff on September 21, 1979, to discuss the relationship of the North Anna Unit 3 and 4 Part 21 notifi-cation filed on September 7, 1979, with the Surry l & 2, North Annal & 2, and Beaver Valley l units.

The Part 21 notification involved the potential overpressurization of containment for a main steam line break if the auxiliary feedwater to the damaged steam generator were not isolated in time to pre-vent a significant contribution of energy from runout of the auxiliary feedwater pumps.

Attendees are listed in Attachment A.

Prior to the meeting, the licensees had been requested to determine the adequacy of their containment analyses. Stone and Webster, on behalf of the licensees, presented the restilts of the existing analyses in answer to NRC questions posed before the meeting. These questions and answers for the facilities involved are summarized in the Attachment B.

As a result of the discussions, it was determined that additional analyses would be required using Beaver Valley Unit No. l and the following assumptions:

1. System runout flow to the damaged steam generator from the auxiliary feedwater systems should be determined and used.

2.

The enthalpy of the steam generator break flow should be 1200 BTU/lb.

(This correlates with an RC pump running.)

3.

Minimum safeguards should be assumed, i.e., one spray train failed.

4.

The analysis should continue until the containment pressure peaks.

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The results obtained for the Beaver Valley Unit No. 1 reanalysis will be reviewed to determine whether additional analyses are warranted for Surry 1 & 2 and similar plants.

Attachments:

A.

Attendance List B.

Summary of Questions and Answers Ali~114'rd=

Dave Wigginton, ~oject Manager Operating Reactors Branch #1 Division of Operating Reactors

e Meeting Summary for Beaver Valley, North Anna & Surry OCTOBER J. (i l8/~

Docket Files NRC PDR Local POR *.

ORB1 Reading NRR Reading H. Denton L Case D. Eisen hut

. G. Zecli B. Grimes W. Gammil 1 L-. Shao J. Mil 1 er R. Vollmer T. J. Carter A.,Schwencer D. Ziemann

• P. Check G. Lainas D. Davis B. Grimes

• T. Ippolito R. Reid-V. Noonan D. Crutchfi'eld

• G. Knighton o~ *Brinkman*

Project Manager DELO OI&E (3)

C. Parrish/P. Kreutzer ACRS (16)

NRC Particip.ants

. J. Buchanan TERA Licensee

'Mr. Jack Carey

• Technical Assistant Dutjuesne Light Company P. O. Box 4

• Shippingport, Pennsylvania 15(

Mr. R. E. Martin Duquesne Light Company 435 Sixth Avenue Pittsburgh, Pennsylvania 15219

• Marvin Fein Utility Counsel City of Pittsburgh 313 City-County Building Pittsburgh~ Penn~ylvani? 15219 Gerald Charnoff, Esquire Jay E. Silberg, Esquire Shaw, Pittman, Potts and Trowbr, dge 1800 M Street, N.W.

Washington, D. C.

20036

-Karin Car,te~, Esquire.

Special Assfstant Attorney General bureau of Administrative Enforcement 5th Floor, *Executive House Harrisburg,,Pennsylvania 17120 Mr. Roger Tapan Stone and Webs~er ~ngineering Corporation P. O. Box 2325 Boston, Massachusetts 02107 Mr. J. O. Woodward R & O.Center Westinghouse Electric Corporation Building 7-303 Pittsb~rgh, Pennsylvania 15230 Mr. James A. Werling.

Pl ant Superintendent Beaver Valley Power Station P. o. Box 4 Shippingport, Pennsylv~nia 15077 Mr. John A~ Levin Public Utility Commission P. 0. Box 3265 Harrisburg, -~ennsylvania 17120 Donald J. Burke

.. u. s~ Nuclear Regulatory Commission Region II

• Office of Inspection and Enforcement 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Mr. Michael W. Maupin Hunton and Williams Post Office Box 1535 Richmond, Virginia 23213

e e

ATTENDANCE LIST A. Schwencer Chief, ORB #1, DOR F. Eltawila NRC/DSS, CSB C. Robertson S&W

w. C. Drotl eff S&W D. H. Wi 11 i ams Duquesne Light Co.

E. s. Grecheck Vepco D. L. Benson Vepco

w. Butler NRC/CSB/DSS L. P. Walker S&W

w. P. Dodson S&W D. A. Piccione S&W C. Grochmal S&W R. Borsum B&W C. Ader S&W E. Thomas S&W F. A. Eli a, Jr.

S&W E. A. Warman s&w*

E. G. Adensam NRC/DOR/PSB E. H. McCall ig S&W H. A. Wilber NRC/IE/DOR A. w. Dromerick NRC/DPM G. L. Lainas NRC/DOR/PSB G. w. Moore DLC F. Salmon DLC D. Wigginton NRC/DOR/ORB #1

NRC QUESTIONS NORTH ANNA 1 ANO 2

1.

IAS AUXILIARY JEEDWATER PUMP RUNOUT CONSlgERED IN CON-TA I NM ENT ANALYSIS?

YES PROVIDE MASS FLOI RATE AND BASIS FOR THIS RATE.

900 GPM (125 LBN/SEC)

ORIFICE DESIGN TO LIMIT FLOI RATE

2.

TIME AFF WAS ASSUMED TO BE ISOLATED 1 BOO SEC ACTIONS RlUUIREO FOR ISOLATION REMOTE MANUAL CLOSURE OF AUXILIARY FEEOLINE VALVE

3.

EFFECTS OF RETURN TO POIER NEGLIGIBLE AOVERSE EFFECT ON CONTAINMENT PRESSURE

4.

PROVIDE PLOT/TASLE OF THE ENTHALPY OF FLUID SEE ATTACHEO TABLE 1 ENTERING CONTAINMENT VERSUS TIME

5.

DESCRIBE SINGLE ACTION FAILURE WHICH MAXIMIZES FAILURE OF NON-RETURN CHECK VALVE CONTAINMENT PRESSURE OESCRIBE HOW THIS FAILURE IMPACTEO ORIGINAL RESULTED IN AOOITIONAL EARLY STEAM RELEASE ANALYSIS CONTAINMENT PEAK PRESSURE OF 45 PSIG WAS REACHED IN 59 SEC.

6.

OESCRIBE CONTAINMENT SPRAY SYSTEM Q. s: 64 SEC., R. S. 304 SEC.

Tl~E OF ACTUATION CAPACITY 0.S.1900 GPM/TRAIN,R.S. 6300 GPM/TRAIN HEAT REMOVAL CAPABILITY SEE TABLE

1.

IS AFF ISOLATION AUTOMATIC?

NO W.AJOR POINTS:

(1).WERE THE ABOVE CONSIOERATIONS INCLUCED IN YES ORIGINAL ANALYSIS?

(2).HAVE ANY DESIGN MOOIFICATIONS BEEN KAOE WHICH WOULO ll!PACT THE ORIGINAL ANALYSIS?

NONE THAT AFFECTED THE PEAK PRESSURE IN THE ANALYSIS SURRY 1 ANO 2 ANALYSIS WAS NOT REQUIRED NOT AVAILA&LE, HOWEVER DATA SHOULD BE SIMILAR TD BEAVER VALLEY 1 NOT APPLICABLE P.ELATIVE TO ANALYSIS ATTENOEE WILL OESCRIBE ACTIONS REQUIRED FOR ISOLATION NEGLIGIBLE ADVERSE EFFECT CN CONTAINMENT PRESSURE NOT AVAILABLE, HOWEVER OATA SHOULO BE SIMILAR TO BEAVER VALLEY I NOT AVAILABLE, HOWEVER DATA SHDULO BE SIMILAR TO BEAVER VALLEY I SURRY 1 SURRY 2 a.s. 58 SEC.,R.S.293 SEC.

Q.S. 85 SEC.. R.S.284 SEC.

0.S.2400GPM/TRAIN Q.S.2000 GPM/TRAIN P..S.5750GPM/TRAIN P..S. 6500 GPM/TRAIN NO NO ORIGINAL ANAYSIS IAS REQUIRED NOT APPLICABLE BEAVER VALLEY 1 YES. RUNOUT FLOW WAS SPLIT EQUALLY TO ALL THREE STEAM GENERATORS 22DD GPM SPLIT TO 727 GPM PEP. STEAM GENERATOR PUMP RUNOUT AT ZERO BACK PRESSURE NO ISOLATION WAS ASSUMEO IN. ANALYSIS ATTENDEE WILL DESCR19E ACTIONS REQUIRED FOR ISOLATION NEGLIGIBLE AOVERSE EFFECT ON CONTAINMENT PRESSURE SEE ATTACHEO TABLE FAILURE OF NDN-RETUP.N CHECK VALVE RESULTED IN ADDITIONAL EARLY STEAM RELEASE CONTAINMENT PEAK PRESSURE OF 38 PS\\G WAS REACHED IN APPROXIMATELY 51 SEC.

U.S. 69 SEC., R.S.305 S!:C, D.S. 2100 GPM/TRAIN, R.S. 6600 GPM/TRAIN SEE TABLE FOR NORTH ANNA 1 l 2

• NO YES NONE THAT AFFECTED THE PEAK PRESSURE IN THE ANALYSIS

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