ML16342B867

Summary of 911218 Meeting W/Util in Rockville,Md Re RG 1.97 Issues Applicable to Facility

ML16342B867
Person / Time
Site:	Diablo Canyon
Issue date:	03/11/1992
From:	Rood H Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
RTR-REGGD-01.097, RTR-REGGD-1.097 TAC-M79787, TAC-M79788, NUDOCS 9203310307
Download: ML16342B867 (46)

Text

Yarch 13.,

1992 Docket Nos. 50-275 and 50-323 LICENSEE:

FACILITY:

SUBJECT:

Pacific Gas and Electric Company (PGSE)

Diablo Canyon Nuclear Power Plant, Units 1 and 2

SUMMARY

OF DECEMBER 18, 1991 MEETING HELD IN ROCKVILLE, MARYLAND TO DISCUSS REGULATORY GUIDE (RG) 1.97 ISSUES APPLICABLE TO DIABLO CANYON (TAC NOS.

M79787 AND M79788)

On December 18, 1991, the NRC staff met with the Pacific Gas and Electric Company (PG8,E) in Rockville, Maryland to discuss the above subject.

Attendees at the meeting are listed in Enclosure 1.

The viewgraphs presented by PGSE at the meeting are given in Enclosure 2.

During the meeting, PGSE indicated that it would propose corrective action to address the three open items from the RG 1.97 inspection that was conducted at Diablo Canyon in 1988 (see Inspection Reports 50-275/88-02 and 50-323/88-02 issued on April 27, 1988).

These open items involve (1) lack of neutron flux recording capability, (2) use of resistors as isolation devices, and (3) lack of power source redundancy for wide range steam generator level instrumentation.

A more recently identified issue involves the adequacy of position indication circuits (the white status light monitoring system) for four RG 1.97 variables.

A solution for this issue is being developed by PG8E and will be based on the results of an ongoing study which is expected to be completed in about six months.

Enclosures:

1.

Attendees 2.

PGImE Viewgraphs cc w/enclosures:

See next page Original Signed By:

Harry Rood, Senior Project Manager Project Directorate V

Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation SNewberry AMarinos BMarcus

PNarbut, RV RZimmerman, RV PMorrill, RV Hl<ong, RV DRPM/PD5 TQuay 03/<</92>

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 March 11, 1992 Docket Nos. 50-275 and 50-323 LICENSEE:

FACILITY:

SUBJECT:

Pacific Gas and Electric Company (PG&E)

Diablo Canyon Nuclear Power Plant, Units 1 and 2

SUMMARY

OF DECEMBER 18, 1991 MEETING HELD IN ROCKVILLE, MARYLAND TO DISCUSS REGULATORY GUIDE (RG),1.97 ISSUES APPLICABLE TO DIABLO CANYON (TAC NOS.

M79787 AND M79788)

On December 18, 1991, the NRC staff met with the Pacific Gas and Electric Company (PG&E) in Rockville, Maryland to discuss the above subject.

Attendees at the meeting are listed in Enclosure 1.

The viewgraphs presented by PG&E at the meeting are given in Enclosure 2.

During the meeting, PG&E indicated that it would propose corrective action to address the three open items from the RG 1.97 inspection that was conducted at Diablo Canyon in 1988 (see Inspection Reports 50-275/88-02 and 50-323/88-02 issued on April 27, 1988).

These open items involve (1) lack of neutron flux recording capability, (2) use of resistors as isolation devices, and (3) lack of power source redundancy for wide range steam generator level instrumentation.

A more recently identified issue involves the adequacy of position indication circuits (the white status light monitoring system) for four PG 1.97 variables.

A solution for this issue is being developed by PG&E and will be based on the results of ar. ongoing study which is expected to be completed in about six months.

Enclosures:

1.

Attendees 2.

PG&E Viewgraphs cc w/enclosures:

See next page Harry R

d, Senior Project Manager Project Directorate V

Division of'eactor Projects III/IV/V Office of Nuclear Reactor Regulation

T

Pacific Gas and Electric Company Diablo Canyon CC:

Regional Administrator, Region V

U.S. Nuclear Regulatory Commission 1450 Vivaria Lane, Suite 210 Walnut Creek, California 94596 Mr. Peter H. Kaufman Deputy Attorney General.

State of California 110 West A Street, Suite 700 San Diego, California 92101 NRC Resident Inspector Diablo Canyon Nuclear Power Plant c/o U.S. Nuclear Regulatory Commission P. 0. Box 369 Avila Beach, California 93424 Richard F. Locke, Esq.

Pacific Gas 5 Electric Company Post Office Box 7442 San Francisco, California 94120 Yir. John Hickman Senior Health Physicist Environmental Radioactive Mgmt. Unit Environmental Management Branch State Department of Health Services

?14 P Street, Room 616 Sacramento, Cal iforni a 95814 Michael M. Strumwasser, Esq.

Special Assistant Attorney General State of California Department of Justice 3580 Wilshire Boulevard, Room 800 Los Angeles, Cali fornia 90010 Managing Editor The Count Tele ram Tribune 1321 Johnson Avenue P. 0. Box 112 San Luis Obispo, California 93406 Chairman San Luis Obispo County Board of Supervisors Room 370 County Government Center San Luis Obispo, California 93408 Ms. Sandra A. Silver.'

Mothers for Peace 660 Granite CreeL-Road Santa Cruz, California 95065 Dr. R. B. Ferguson, Energy Chair Sierra Club California 6715 Rocky Canyon

Creston, Cali fornia 93432 Ms. Nancy Culver 192 Luneta Street San Luis Obispo, California 93401 Ms. Jacquelyn C. Wheeler 3303 Barranca Court San Luis Obispo, California 93401 Mr. Gregory M. Rueger Senior Vice President and General Manager Nuclear Power Generation Business Unit Pacific Gas and Electric Company 77 Beale Street, Room 1451 San Francisco, CA 94106

ENCLOSURE 1

Attendees December 18, 1991 Meeting to discuss Regulatory Guide 1.97 issues NAME Ws Fu Jlmoto B. Marcus A. Marinos P. Narbut S.

Newberry H.

Rood J.

Tomkins R.

Webb ORGANIZATION NRC/NRR/DST/SICB NRC/NRR/DST/SICB NRC/RV NRC/NRR/DST/SICB NRC/NRR/DRPW/PD5 PGGE PG&E

ENCLOSURE 2

Yiengr a phs Presented by PGEE December 18, 1991 Yieeting to discuss Regulatory Guide 1.97 issues

PACIFIC GAS ANO ELECTRIC NRC STAFF MEETING DECEMBER /8, 1991 Resolution of RG 1.P'7 Post-Accident Monitoring Instrumentation Issues

PURPOSE OF MEETING Resolve RG 1.97 open items and issues Identified during 1988 NRC RG 1.97 implementation audit Identified by PG&E during nonconformance review and design basis reconstitution

RG 1.97 BACKGROUND Dec.

1975 Aug. 1977 Dec.

1980 Oct.

1981 May 1983 Sept.

1983 June 1984 RG 1.97 issued by NRC RG 1.97 Rev.

1 issued RG 1.97 Rev.

2 issued PGBE letter to NRC identifying Diablo Canyon changes necessary for compliance with RG 1.97 Rev.

2 RG 1.97 Rev.

3 issued PG8E letter to NRC c'ommittirtg'to RG 1.9?

Rev.

3 NRC letter to PGBE requestin~'

justification for DCPP exceptions to RG 1.97

'1

RG 1.97 BACKGROUND (CONTINUED 4'1)

Sept.

1984 Oct. 1984 Apr. 1988 May 1988 May 1989 PG&E letter to NRC responds to questions NRC issues DCPP SSER-31 accepting PG&E's RG 1.97 submittal NRC RG 1.97 implementation audit results in NOD for lack of redundant power.

supplies to wide range (WR) steam generator (SG) level indication.

Three unresolved items identified.

PG&E responds to NOD and unresolved items providing justification for existing installations Nonconformance 89-N009 issued due to Class II WR SG level recorder power supply identified during design change process for replacement of recorders

"N

RG 1.97 BACKGROUND (CONTINUEO 4'2)

Sept.

1989 July 1990 Jan.

1991 K

Nonconformance 89-N009 lead=-

to engineering review of all cabling and power supplies for RG 1.97 category 1

and 2 loops Completed screening and identified potential concern with position indication Nonconformance 91-N005 issued due to concerns with position indication circuits for four of seventy-two RG 1.97 variables Jan.

July 1991 Circuit by circuit review performed for all attributes required by each indicator.

Discrepancies identified/confirmed as not safety significant

0

VALVEPOSITION INDICATfON Red%green lights:

Control board status light;..

next to control switch normally used by operators when valve position is changed White status light monitoring system:

Monitor boxes for display of reactor protection and safeguard signals and containment isolation valve position

RG 1.97 BACKGROUIVQ (CONTINUEO 4'9)

Aug. -

Personnel interviews performed to review Sept.

1991 history and determine root cause Oct.

1991 Nov.

1991 Nov.

1991 PGBE letter to NRC providing additional information to resolve unresolved inspection item on RG 1.97 isolation devices Operability Evaluation performed for issues covered by nonconformance 91-N005 confirms previous conclusions of operability and low-safety significance PGBE letter informing NRC of inconsistencies between the as-installed instrumentation and commitment for four of seventy-two RG 1.97 variables

RG f.97 /SSUES

~

Identified during 1988 NRC audit:

- Wide range-steam generator level power supply redundancy

- Resistor networks used as isolation devices

- Neutron flux monitor continuous recording

~

Identified during PG8E nonconformance process and design basis reconstitution:

- Variable 15

- Variable 34

- Variable 53 Variable 63 Containment isolation valve position indication Accumulator isolation valve position indication Containment-fan heat removal system indication Emergency damper position indication

SUMMARY

OF PGBE IDENTIFlED RG 1.97 ISSUES

~ Variable 15 Containment isolation valve position indication RG 1.97 specifies Class 1B, Category 1

EQ/EQ file issues Seismic qualification file issues Separation/Isolation issues Emergency Operating Proceduie (FOPs) issues

I TYPICAL CIV WITH CONNECTIONS TO WHITE LIGHT.BOX CONTAINMENT INSIDE OUTS I DE POSITION SM CLASS IE (TYPICAL)

FCV (GENERIC)

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RED/GRN L'GHTS CONTROL ROOM SINGLE POWER SOURCE

~ REDUNDANCY WHITE L I GHT BOX CLASS IE WHITE LIGHT ISSUES PREFAB CABLE SEPARATION SEISMIC i ISOLATION REDUNDANCY CABLE SPREADING ROOM CLASS IE RED/GRN LIGHT ISSUES BTHIIO RELAY CABIhfET

-SEISMIC

~ SEPARATION S-5

CONTA I NMENT INSIDE OUTSIDE TYPICAL LIQUID RADMASTE 'IV ISSUES CLASS IE WHITE LIGHT I

I I

WHITE LIGHT BOX FCV 253 FCV 254 SOL VALVE PWR CABLE CLASS IE ISSUE:

~,CLASS 2 TRAY CABLE

~ REDUNDANCY SEPARATION

~ ISOLATION NON-FULL SEISMIC RED/GRN LIGHT BTHIIO RELAY CABINET L

Xp CONTROL ROOM NON-I E SINGLE PREFAB CABLE CABLE SPREADING ROOM ISSUE

~,FCV 254 i NON-CLASS IE

. WHITE LIGHT SEPARATION

~ REDUNDANCY ISOLATION AUXILIARY BUILDING 0

RED/GRN FCV 253 POLR I I 0

RED/GRN FCV 254 POLRI2 IE POWER SOURCE RED/GRN TOTAL LR VALVES WITH THIS DESIGN:

9 LIQUID RADWASTE CONTROL PANELS CLASS IE

t VARIABLE15 (CON TINLi "ED)

Affected containment penetrations incl:;~de:

- Five liquid radwaste penetrations

- One CVCS letdown line penetration

- Two penetrations for incore chilled water Two penetrations for containment air to/from post-LOCA sampling system

, t

SUMMARY

OF PG8E IDENTIFIED RG 1.97 ISSUES (CONTINUEO)

~ Variable 34 Accumulator isolation valve position indication RG 1.97 specifies Class 1B, Category 2

- Design is Class 1B, Category 3

~ Variable 53 Containment fan heat removal system indication RG 1.97 specifies Class 1B, Category 2

- Part of design is Class 1B, Category 3

~ Variable 63 Emergency damper position ihdication RG 1.97 specifies Class 1B, Category Circuits for certain control room ventilation dampers are not powered from'ighly reliable power sources

OPERABILITYANO SAFETY EYALUATIION FOR EXISTING OESIGN

~ PGLE performed an operability evaluatior; (OE) that included a 50.59 safety evaluation I

~ Conclusion of OE is that the RG 1.97 monitoring system will fulfill its specified

function, c~r there exists alternate means for compliance with RG 1.97

I If

PG8E ACTIONS TO RESOLVE ISSUES Inspection Issues

~ Wide range steam generator level power supply redundancy PG&E will change two loops to a

sepa<'a'.:e channel to provide single failure proof indication

~ Resistor networks used as isolation devices PG8E has committed to installation of isolation devices tested and qualified as part of the Eagle 21 plant protection system

~ Neutron flux monitor continuous recording PG&E will install recorders for the neutron flux variables

t

PG8E ACTIONS TO RESOLVE ISSUES (CONTINUED 4'1)

'i PGBE identified Issues

~ Variable 15 Containment isolation valve position indication PG8E will upgrade the white light monitoring system to meet RG 1.97 functional requirements and request exceptions where appropriate

~ Variable 34, Accumulator isolation valve position indication PG8E will request an exception to the RG 1.97 EQ requirement

PGBE ACTIONS TO RESOLV'::= ISSUES (CONTINUED N2)

PG8E Identified Issues

~ Variable 53 Containment fan heat removal system operability PG8E will implement a design change to lock dampers in accident position.

License Amendment Request is pending NRC approval

~ Variable 63 Emergency damper position indication PGBE has completed a design change to provide highly reliable power to.".ertain emergency damper position indic~tion circuits

SUMMARY

OF ACTIONS AND SCHEDUI E

~ Diablo Canyon changes will be implemented Wide range steam generator level power supply redundancy design change

{with Eagle 21) isolation devices installed

{with Eagle 21)

ECD-Unit 1, May 1994, Unit 2, Dec.

1994 Neutron flux monitoring recorders installed.

ECD-Unit 1, May 1994, Unit 2; l3~.c.

1994 Emergency damper position indicatIan power supply design change.

ECD-complete Containment isolation valve positior. indication design upgrade.

ECD-Dec.

1995, tV'.'ay 1996