IR 05000309/1985025

Enforcement Conference Rept 50-309/85-25 on 850909.Areas Discussed:Isolation of Nine Steam Generator Pressure Transmitters & Inoperability of Channel a Low Steam Generator Trip Function.Viewgraphs Encl

ML20137Y934
Person / Time
Site:	Maine Yankee
Issue date:	09/26/1985
From:	Elsasser T, Wenzinger E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20137Y919	List: IR 05000309/1985025 ML20137Y913
References
50-309-85-25-EC, NUDOCS 8510080121
Download: ML20137Y934 (23)

Text

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Docket / Report: 50-309/85-25 License: DPR-35

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Licensee: Maine Yankee Atomic Power Company 83 Edison Drive

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Augusta, Maine 04336 l

l Facility: Maine Yankee Atomic Power Plant l

l Meeting Date: September 9 ,198 #

Reported by: /- -

w- Jf[85 1. C s sseh~dC,Hief , Reactor Projects Section 3C Date Approved by: pfW/~ 8 d5'

E. C. Wenzi6ger, le Projects Branch No. 3 Date l Summa ry:

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An Enforcement Conference was conducted in the NRC Region I Office to discuss the l circumstances surrounding the discovery of nine shut root isolation valves for the Steam Generator Pressure Transmitters which rendered pressure Channels B, C, and D and their associated protective functions inoperable. Also discussed was the i

discovery of the inoperability of the Channel A Steam Generator Low Pressure trip I function for the Reactor Protective System due to an inadequate design modification.

l The root cause of the events and the corrective action to prevent recurrence were outlined by the licensee. The corrective actions included an in-depth plan for

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control of all root valves as well as a review of past plant modifications and a l functional test program to evaluate proper installation of those modifications.

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VDH

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DETAILS Meeting Attendees Maine Yankee Atomic Power Company J. B. Randazza, Executive Vice President C. D. Frizzle, Vice President - Manager of Operations E. T. Boulette, Assistant Plant Manager G. D. Whittier, Manager, Nuclear Engineering and Licensing *

Yankee Atomic Electric Company P. L. Anderson, Maine Yankee Project Manager P. A. Bergeron, Manager, Transient Analysis W. H. Reed, I&C Lead Engineer USNRC T. E. Murley, Regional Administrator, Region !

J. M. Allan, Deputy Regional Administrator, Region I W. F. Kane, Ooputy Ofrector, Olvision of Reactor Projects (DPR), Region !

J. Gutierrez, Regional Counsel, Region !

D. Holody, Enforcement Specialist, Region !

E. C. Wenzinger, Chief, Projects Branch No. 3, ORP, Region I T. C. Elsasser, Chief, Reactor Projects Section 3C, DRP, Region !

L. Bettonhausen, Chief, Operations Branch, Division of Reactor Safety (DRS)

ReOlon 1 J. R. Johnson, Chief, Operational Programs Section DRS, Region !

E. Butcher, Acting Chief, Operating Reactors Oranch No. 3 Division of Licensing NRR P. K. Eapen, Chlef, Quality Assurance, DRS, Region !

C. Holden. Senior Resident Inspector 2. Moctina Purpose To discuss the circumstances surrounding the discovery of nine shut root valves for the Steam Generator Pressure Transmitters associated with pressure Channels H. C, and D, and the discovery of an inoperable Channel A Steam Gen-erator Low Pressure trip function for the Reactor Protective System due to an inadequate design modificatio . Items Discuened ihn following items were discussed:

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Circumstances surrounding the two event Root causes that contributed to the event . _ _ _ _ _ - _ -

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Safety significance of an inoperable Steam Generator Pressure functio !

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The potential effect of design review and testing deficiencies on plant systems as a result of past and current modification Corrective action, both short and long term, taken to resolve both events, t

' Results At the meeting, the licensee agreed to submit to NRC Region I formal documen- '

tation of those corrective actions presented at the Enforcement Conference l which will be implemented to correct and prevent recurrence of these event l Attached to this report are the viewgraphs presented during the meeting.

l Several of these viewgraphs outline the licensee's proposed corrective ac-  !

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- ALL.12 ROOT VALVES CLOSED

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2. NO SPECIFIC REQUIREMENTS FOR OPENING ROOT STOP VALVES

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'. ..CHANNELa"A"., ROOT VALVES OPENED

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IMMEDIATE CORRECTIVE ACTIONS

' 1. VERIFY OPEN OR OPEN ALL S/G PRESSURE ROOT VALVES 1.2. WHITE TAG ALL S/G PRESSURE ROOT VALVES

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VERIFICATION OF FULL COMPLIANCE l

1. IDENTIFY ALL ROOT VALVES IN T.S. TABLE 4.1-1,-2,-3 (RPS,ESF,ETC.)

2. VERIFY OPEN/ WHITE TAG ALL ACCESSIBLE ROOT. VALVE .

. 3. IDENTIFY THOSE ALREADY UNDER ADMI CONTROLS AND VERIFY OPEN

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4. VERIFY OPEN INACCESSIBLE ROOT VALVES BY OBSERVANCE OF ASSOCIATED INSTRUMENTATION, POST MORTEMS,

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CHART. RECORDINGS, SEQUENCE OF

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.?,5;NERIFY' ADEQUATE ADMINi. CONTROLS.ON. ALL

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ACTIONS TO PRECLUDE RECURRENCE

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1. REVISE PROCEDURES TO GOVERN POSITION OF ALL T.S. TABLES 4.1-1,-2,-3 ROOT VALVES l 2. REVIEW ALL TEMPORARY PROCEDURES FOR APPROPRIATE VALVE POSITIONING d

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3. REFUELING OUTAGE VERIFICATION OF

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, OPEN POSITION 4. REVISION OF PROCEDURE GOVERNING i

.. . PREPARATION OF PROCEDURES TO ENSURE EXPLICIT DEFINITION OF

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BEST ESTIMATE ASSESSMENT OF CONSEQUENCES

TRANSIENTS IMPACTED

EQUIPMENT ASSUMED DISABLED

EQUIPMENT CREDITED

ANALYSIS PERFORMED

RESULTS

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9720N-CDF-85-5'l

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TRANSIENTS IMPACTED

CONSIDERED TRANSIENTS AND ACCIDENTS DEFINED IN CHAPTER 14 0F FSAR

ONLY EVENT IMPACTED ARE SEVERE OVERC00 LING TRANSIENTS E.G. MAIN STEAM LINE BREAK (MSLB)

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9720N-CDF-85-54

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EQUIPMENT ASSUMED DISABLED

• LOW STEAM GENERATOR (SG) PRESSURE TRIP (RPS)

MAIN FEEDWATER PUMP TRIPS ON LOW SG PRESSURE COINCIDENT WITH SIAS

MAIN AND AUX FEEDWATER ISOLATION TO RUPTURED STEAM GENERATOR ON LOW SG PRESSURE

EFCV'S REMAIN OPEN THROUGHOUT TRANSIENT

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EQUIPMENT CREDITED

RPS TRIPS OTHER THAN LOW SG PRESSURE

NRV'S FOR UPSTREAM BREAKS INSIDE CONTAINMENT

• FW REG. VALVE CLOSURE ON REACTOR TRIP / TURBINE TRIP FOR UPSTREAM BREAKS

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• N-CDF-85-54

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ANALYSIS PERFORMED

DOUBLE-ENDED RUPTURE OF MAIN STEAM LINE (UPSTREAM AND DOWNSTREAM 0F. EFCV's)

ASSESSMENT OF SEQUENCE OF BACKUP REACTOR TRIPS

POTENTIAL FAILED FUEL FROM A RETURN-TO-POWER AT E0C

P0TENTIAL FOR CONTAINMENT OVERPRESSURE FOR UPSTREAM BREAKS t

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RESULTS

BACKUP REACTOR TRIPS

TYPICALLY LOW SG PRESSURE TRIP WOULD OCCUR - 2 SECONDS FOR MSLB

DELTA T POWER - <10 SE *

HIGH NUCLEAR FLUX * -<C10 SE *

LOW RCS PRESSURE -<(15 SE *

CONTAINMENT PRESSURE (5 PSIG) -<(5 SE *

. SG LEVEL - (INSTANTANE0US?)

• DEPENDENT ON BURNUP

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9720N-CDF-85-54

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RESULTS

RETURN-TO-POWER

BEST ESTIMATE REACTIVITY BALANCE (HFP & HZP)

CEA WORTH AVAILABLE

MODERATOR DEFECT T0 60*F

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D0PPLER DEFECT T0 60*F

MAXIMUM STUCK R0D

NO CREDIT FOR BORON INJECTION (FROM SI)

0.3% DELTA RH0 SUBCRITICAL i

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97,].0N-CDF-85-54

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RESULTS

CONTAINMENT PRESSURE

NRV LIMITS BLOWDOWN TO ONE SG

TURBINE TRIP CLOSURE ON FWRV LIMITS FEEDWATER TO WITHIN LICENSING ANALYSIS i

PEAK PRESSURE DESIGN OF 55 PSIG i

9720N-CDF-85-54

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DESIGN CHANGE PROCESS REVISIONS l MODIFY DESIGN CHANGE INPUT REQUIREMENTS TO SPECIFICALLY l

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IDENTIFY INSTRUMENTATION COMMONING AS AN AREA THAT REQUIRES SPECIAL DESIGN AND DESIGN REVIEW EMPHASI I MODIFY DESIGN CHANGE FUNCTIONAL TEST REQUIREMENTS TO SPECIFY MORE COMPREHENSIVE FUNCTIONAL TEST FUNCTIONAL TESTS SHOULD G0 BEYOND THE MODIFIED CIRCUIT TO INCLUDE INTERACTIVE CIRCUIT Il INDEPENDENT REVIEW BY COMBUSTION ENGINEERING OF ALL DESIGN CHANGES WHICH AFFECT THE REACTOR PROTECTIVE SYSTEM OR THE ECCS ACTUATION SYSTEMS.

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FUNCTIONAL TEST PROGRAM SCOPE SYSTEMS IDENTIFIED IN TABLE 4.1 0F TECH. SPEC COMPLETE TEST (INPUT TO FINAL ACTION) AS PRACTICAL I METHOD TEST OBJECTIVE COMMITTEE MULTIDISCIPLINED COMMITTEE TO REVIEW FSAR DESIGN REQUIREMENTS AND OUTLINE APPROPRIATE TEST OBJECTIVE TEST PROCEDURE PREPARATION AND REVIEW TASK FORCE CONSISTING OF MY, YNSD AND CE PERSONNEL TO PREPARE AND/0R REVIEW EXISTING FUNCTIONAL TEST PROCEDURES TO ENSURE TEST OBJECTIVES ARE ME Il IMPLEMENTATION

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ALL FUNCTIONAL TESTS COMPLETED AND DOCUMENTED PRIOR TO PLANT POWER OPERATIO .

9720N-CDF-85-54

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II TO PREVENT RECURRENCE DESIGN CHANGE PROCESS REVISIONS

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9720N-CDF-85-54

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CORRECTIVE ACTIONS 1. IDENTIFY ROOT CAUSE

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DESIGN REVIEW SCOPE ALL DESIGN CHANGES WHICH INVOLVE DIRECTLY OR INTERACT WITH THE SYSTEMS LISTED IN TECH. SPEC. I PURPOSE REVIEW FOR POTENTIAL "COMMONING" PROBLEMS REVIEW FOR ANY OTHER " INTERACTION" PROBLEMS II RESPONSIBILITY YNSD I INDEPENDENT REVIEW COMBUSTION ENGINEERING

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9720N-CDF-85-54