ML20237B690

Summary of 871122 Site Meeting W/Util Re Technical Issues Concerning Scram Experience & Efforts to Reduce Frequency of Future Scrams.Related Info Encl

ML20237B690
Person / Time
Site:	Beaver Valley
Issue date:	12/04/1987
From:	Tam P Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TAC-66620, NUDOCS 8712170068
Download: ML20237B690 (13)

Text

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December 4,1987 s

Docket No. 50-412 LICENSEE: Duquesne Light Company FACILITY: Beaver Valley Unit 2

SUMMARY

OF MEETING HELD ON NOVEMBER 22, 1987 (TAC 66620)

The subject meeting was held at the plant site to discuss with licensee personnel the technical issues related to the unit's scram experience, and the l licensee's efforts to reduce frequency of future scrams. Enclosure 1 lists j the meeting attendees. Enclosure 2 is the meeting notice.

The licensee has summarized the unit's scram experience in Enclosure 3. All the scrams, except the last three listed and the one that occurred on ,

November 17, have been documented in Licensee Event Reports (LERs). In these '

LERs, the licensee also addressed corrective measures already implemented or i planned. The staff pointed out that evaluation of these scrams up to 1 October 9, and assessment of the licensee's corrective measures, have been documented in Inspection Reports 50-412/87-47, -54 and -60.

The most recent scram (November 17,1987) was nct listed in Enclosure 3. The staff noted that a team of NRC specialists was onsite at that time to evaluate the incident, one that involved loss-of-offsite pow r and reactor coolant natural circulation. The licensee presented a description of the incident and stated that it will be documented in an upcoming LER.

The attendees discussed the support provided to the licensee by Westinghouse, specifically, if better support could have averted some of the scrams. The licensee stated that because the unit is going from the engineering / construction mode of operation to coninercial operation, the nature and degree of dependence on vendors are also in transition. Therefore, the situations under which some of the scrams occurred would not be repeated.

In conclusion, the licensee stated that (1) despite the relatively large number of scrams, there was no recurrent problem, (2) with the exception of modification of the main feedwater regulating valves for more stable control, all other modifications to preclude recurrence of past scrams have been completed, and (3) some of the scrams can only happen at a reactor with a new core or during startup testing of a new reactor.

8712170060 a71204 12 DR ADOCK 0500

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P 2-The staff noted that the most: import' ant _ lesson learned would be the need.to apply operating experience at the first unit to design / engineering of.a second unit, In the case of Beaver Valley, this may have eliminated the scrams

c. caused by' feedwater instability.

Wd&d $??@ IWf' Peter S. Tam, Project Manager Project Directorate I-4 Division of. Reactor Pro;fects I/II i

Enclosures:

As stated cc w/ enclosures:-

See next page t

h$ l OFC :DRP:PDI4/LA :DRP:PDI4/PM .:DRP:PDI4/P Y"  :-  :  :

NAME-:SMNorris  :  :  :  :

PSTam:ah{s{:JFStol2

.____: .....______:__________._:____f.__3,..:_____.._____ __________...____...___..___.....___

DATE :12/~7/87' :12/S/87 :12/(/87  :  :  :  :

OFFICIAL. RECORD COPY h

_ _ _ = _ _ _ _ _ _ _ - - _ - - _ - _ - _ __ _ - - - _ . - - - - _ - - - - -- - - - . - - - - ------------------J

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1 Mr. J. J. Carey Duquesne Light Company Beaver Valley 2 Power Station CC:

Gerald Charnoff, Esq. Mr. Kenneth Grada, Manager

. Jay'E. Silberg, Esq. Safety and Licensing, Shaw, Pittman, Potts & Trowbridge Duquesne Light Company 2300 N' Street, N.W. P. O. Box 4 ,

Washington, DC 20037 Shippingport, Pennsylvania '15077 Mr. C. W. Ewing, Quality' Assurance Pennsylvania Office of Consumer

. Manager Advocate Quality Assurance Department ATTN: Michael Bardee  ;

Duquesne Light Company 1425 Strawberry Square -  ;

P. O. Box'186 -Harrisburg, Pennsylvania 17120 Shippingport, Pennsylvania 15077 John D. Burrows, P.E.

Director, Pennsylvania Emergency Director of Utilities Management Agency State of Ohio Room B-151 Public Utilities Comission Transportation & Safety Building IBO East Broad Street Harrisburg, Pennsylvania 17120 Columbus, Ohio 43266-0573; Mr. T. J. Lex Bureau of Radiation Protection Westinghouse Electric Corporation PA Department of Environmental Power Systems Resources P. O. Box 355 -

ATTN: R. Janati Pittsburgh, Pennsylvania 15230 P.O. Box 2063 Harrisburg, Pennsylvania 17120 Mr. P. RaySircar Stone & Webster Engineering Corporation BVPS-2 Records Management Supervisor P. O. Box 23?5 Duquesne Light Company Boston, Massachusetts 02107 Post Office Box 4 Shippingport, Pennsylvania 15077 Mr. J. Beall U. S. NRC John-A. Lee, Esq. ,

P. O. 1B1 Duquesne Light Company Shippingport, Pennsylvania 15077 10xford Centre 301 Grant Street Regional Administrator, Region I Pittsburgh, Pennsylvania 15279 ,

U.S. Nuclear Regulatory Comission 631 Park Avenue King of Prussia, Pennsylvania 19406 1

• MEETING

SUMMARY

DISTRIBUTION 1

'Jibocketi: File" l

NRC & Local PDRs l SVarga BDoger PTam OGC-Bethesda EJcrdan JPartlow ACRS(10)

HBClayton NRC Participants L. Tript P. l fen u__________ _ _ i

ENCLOSURE 1 ATTENDEES AT THE BEAVER VALLEY UNIT 2 MEETING NOVEMBER 22, 1987 1:00 PM i). Sieber Vice President, DLC l J. Crockett Senior Manager, DLC <  !

K. Grada Senior Manager DLC l

L. Tripp Section Chief, NRC Region I J. Beall BV Senior Resident inspector P. Tam NRC Project Manager

, J. Stolz NRC Project Director P. Wen ' Inspector, NRC Region I l

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.. i ENCLOSURE 2 jv'#" S~q' UNITED STATES p- t NUCLEAR REGULATORY COMMISSION j .$ WASHINGTON, D. C. 20555

• November 13, 1987

....+

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Docket No. 50 A1P MEMORANDUM-FOR:

John F. Stolz, Director Project Directorate I A Division of Reactor Projects - I/II FROM:

Peter S. Tam, Project Manager Project Directorate I A Division of Reactor Projects - I/II FORTHCOMING MEETING AT BEAVER YALLEY, UNIT ?

SUBJECT:

DATE & TIME: Friday, November PO, 19P,7 1:00 p.m.

LOCATION:

Beaver Valley Power Station Administration Eldg., Senior VP's Conference Room Shippingpert, PA PURPOSE: To discuss technical issues related to the unit's scram (trip) experience, and the licensee's efforts to reduce frequency of future scrams.

NRC DLCo PARTICIPANTS:

J. Stolz J. Sieber P. Tam, et al. K. Grada, et al.

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i PeNer S. Tam, Project Manager Project Directorate I-4 Division of Reactor Projects - I/II cc: See next page

• Neetings between NPC technical staff and applicants or licensees are open fer interested members n# the public, petitioners, interveners, or nther parties to attend as observers pursuant to "Open Meeting Statement of NRC Staff Policy,"

43 Federal Reaister 28058, 6/28/78. The facility tour may not be open to the public. Interested persons should contact the NRC Project Manager, Peter Tam, at (301) 49?-4837 at least two working days in advance of the meeting.

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SUMMARY

1. While the total number of reactor trips is high (20), utilizing l the INPO criteria, manual trips (15% of total) and sub-critical {

(20% of total) are excluded from the data base.

Moreover, l trips plants are not included in the data base until after their first )

This would reduce the total number of trips j year of operation.

to 13 since (3) reactor trips were manually initiated and (4) i l

occurred during shutdown. One additional trip has occurred since commercial operation on 11/17/87.

2. Only one of the reactor trips, caused by equipment failure, had a  !

recurrent problem (trip numbers 5 and 6) and this was due, in l part, to the intermittent failing of the thyristor. l

3. With the exception of modifying the main feedwater regulating valves fcr more stable control, all other modifications that have been precursors to reactor trips have been completed.

4. All reactor trips (35%) at high power levels (>50%) have been caused by testing, design problems or equipment failures. 65% of the total number of trips occurred below 35% power.

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. .. . NUREG-1275 COMPARISON This section' compares Beaver Valley 2 performance to four other facilities with . Westinghouse NSSS and Turbine Generators 'as identified in NUREG-1275.

I i

REACTOR TRIPS l

OL to Criticality FPL to Criticality to FPL Commercial TOTAL Plant'A 0 1 10 11 Plant B 0 3 9 12 Plant C 0 1 17 18 Plant D 0 0 22 22 BV2 2 2 16 20 ESF ACTUATIONS OL to Criticality FPL to Criticality to FPL Commercial TOTAL Plant A 1 1 3 5

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Plant B 8 9 8 25 Plant C 5 1 14 20 l Plant D 0 44 30 74 BV2 6 1 2 9 LER 87-005 LER 87-009 LER 87-011 LER 87-013 LER 87-016 LER 87-017 LER 87-022 LER 87-024 LER 87-025 l

F .... ..

l ' '.

. NJmEG-1275 Comparison, (Cont'd)

TS VIOLATIONS I

OL to Criticality FPL to Criticality ,to FPL Commercial TOTAL Plant A 8 1 22 31 Plant B 9 4 8 21 Plant C 1 0 13 14 Plant D 21 2 23 46 BV2 1 1 3 5 LER 87-004 LER 87-008 LER 87-021 LER 87-027 LER 87-033 LOSS OF SAFETY SYSTEM FUNCTION OL to Criticality FPL to Criticality to FPL Commercial TOTAL Plant A 1 0 3 4 Plant B 3 0 2 5 Plant C 0 0 2 2 3 0 1 4 Plant D BV2 2 0 0 2 LER 87-006 LER 87-007

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