ML20237F903

Summary of 870804 Meeting W/Util,Fauske & Assoc,Inc & Operations Engineering,Inc to Discuss Emergency Operating Procedures Program & Util Plans for Installation of Direct Torus Vent

ML20237F903
Person / Time
Site:	Pilgrim
Issue date:	08/11/1987
From:	Wessman R Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8708130222
Download: ML20237F903 (22)

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-August-llo 1937

Docket No. 50-293 i 1

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MEMORANDUM FOR: File FROM:- Richard H. Wessman, Senior Project Manager Project Directorate I-3 i Division of Reactor Projects I/II

SUBJECT:

MEETING MINUTES - MEETING BETWEEN BOSTON EDISON COMPANY .

AND NRC ON AUGUST 4, 1987 l On August 4,1987, representatives of Boston Edison Company (BECo) met with members of NRR to discuss issues regarding the Pilgrim Nuclear Power Station. 1 These issues included the Pilgrim, Emergency Operating Procedures Program and '1 the licensee's plans for installation of a Direct Torus Vent. The licensee's presentation is attached as Enclosure 1. Significant matters discussed are summarized on Enclosure 2 to this memorandum. Attendees are listed on Enclosure 3 to this memorandum.

4 Richard H. Wessman, Senior Project Manager.

Project Directorate I-3 Division of Reactor Projects I/II Er. closures:

As stated cc: See attached DISTRIBUTION:

PDI-3 R/F S. Varga B. Boger PDR/LPDR R. Wessman

0. Gormley J. Wiggings, RI Meeting Attendees 4 Docket 150-293; -

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DATE :08/ u /87 :08/// /87  :  :  :  : .

OFFICIAL RECORD COPY l

B708130222 870811 3 DR ADOCK 0500

Enclosure 1 l

- AGENDA -

E0P Heeting: BECo and NRC August 4, 1987

1. Introduction II. E0P Development Process

• PGP Documents

• E0P's Verification / Validation

• Operator Training III. Status of E0P Preparation and Schedule for Implementation IV. Incorporation of SEP Modifications in E0P's Attendees:

Boston Edison:

J. E. Howard, VP-NE&QA 1

C. S. Brennion, Project Engineer - Nuclear Engineering Department J. P. Gerety, Project Engineer - Nuclear Operations Department Fauske & Associates, Inc.:

R. E. Henry Operations Engineering Int:

S. T. Rogers, Executive Consultant l

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OPERATIONS ENGINEERING, INC.

LEAD FOR DOCUMENT PREPARATION PERFORMED CALCULATIONS DEVELOPED AND PRESENTED TRAINING SESSION ON PSTG BASES AND CONTENT TO BECO NUCLEAR ENGINEERING DEPARTMENT PERSONNEL i

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SPP.AY TO PROTECT THE CORE COOLING FUNCTIONS -l 1

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l PILGRIM SAFETY ENHANCEMENT PROGRAM INCLUDES l l

o 8" VENT FROM THE WETWELL GAS SPACE o FIRE WATER TIE-IN TO THE DRYWELL AND SUPPRESSION POOL SPRAY HEADERS AS WELL TO THE LOW PRESSURE l

l CORE INJECTION LINE TO THE REACTOR VESSEL 1

o REDUCED NUMBER OF N0ZZLES FOR THE DRYWELL SPRAYS I WITH THE SAME NUMBER OF N0ZZLE HEADS

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WETWELL VENT PRINCIPAL FUNCTION OF THE WETWELL VENT IS TO PROVIDE PRIMARY CONTAINMENT PRESSUE CONTROL AS DICTATED BY THE.

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(A) MAlhTAINS CONTAINMENT INTEGRITY (B) PRESERVES THE CORE COOLING FUNCTION (c) SERVES AS A CONTAINMENT HEAT REMOVAL MECHANISM 1

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1 i i FIRE WATER TIE-IN o PROVIDES A SEPARATE DIESEL DRIVEN WATER SOURCE FOR INJECTION TO THE RPV AND THE CONTAINMENT l

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PROVIDES WATER TO THE RPV (THE FAVORED PATH) AS WELL l AS TO THE DisYWELL Af;D WETWELL SPRAYS l l

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o PROVIDES SUFFICIENT WATER FLOW TO REMOVE HEAT BY STEAMING (~ 150 GPM) OR BY SENSIBLE HEAT INCREASE IN THE WATER (~1500 GPM)'.

o PROVIDES FOR UNIFORM SPRAY DISTRIBUTION EVEN WITH THE FIRE WATER FLOW RATES  !

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i CONTAINMENT SPRAYS PRINCIPAL FUNCTION OF THE CONTAINMENT SPRAY IS TO PROVIDEFORCONTPNMEIiTTEl1PERATUREC0fiTROLASDICTATED BY THE E0Ps,

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i CONCLUSIONS THE WETWELL VENT AND THE FIRE WATER TIE-IN TO RPV

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INJECTION AND CONTAINMENT SPRAYS, IN CONJUNCTION WITH )

THE E0Ps, PROVIDES SUBSTANTIAL ADDITIONAL PROTECTION AGAINST DAMAGE OF THE REACTOR CORE. THIS IS PRINCIPALLY l DUE T0:

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l o MAINTAINING CONTAINMENT INTEGRITY AND ADEQUATE CORE COOLING BY USING THE WETWELL VENT.

o INJECTION OF WATER TO THE RPV THROUGH THE FIRE WATER TIE-IN TO MAINTAIN ADEQUATE CORE COOLING.

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Enclosure 2 Meeting to Discuss Emergency Operating Procedures and Direct Torus Vent Modification I. Emernency Operating Procedures l

Boston Edison Company (BECo) provided the staff an overview of  ;

their Emergency Operating Procedure (EOP) development program. l The licensee's presentation is provided as Enclosure 1. BECo i discussed the BECo EOP development process, the status of EOP  ;

preparation and schedule for implementation, and their plans for i incorporation of Safety Enhancement Program (SEP) modifications into the EOP's.

BECo advised the staff that their submittal of December 26, 1985, )

regarding the Procedures Generation Package (PGP) has been rendered obsolete by their further development in this area.

BECo agreed to formally submit their revised PGP for staff review and approval. The submittal is expected subsequent to facility l restart. To facilitate staff understanding of their procedure development effort, BECo will make draft copies of the PGP available. This includes the writer's guide, verification and validation procedures, and (when available) training program procedures. l BECo is scheduled to complete the EOPs, classroom training, simulator training and the preliminary verification and validation effort prior to restart. The EOPs are being written l to Revision 4 of the Emergency Procedure Guidelines (EPGs). Even though staff approval of Revision 4 of the EPGs has not been I

issued, the staff review has progressed sufficiently that the NRC l endorses this effort by BECo. However, the staff stated that the

! containment venting philosophy is still under review.

Additional EOP revision, and associated verification and validation, is expected subsequent to restart. Some portions of the EOP's affected by the SEP modifications will be revised after facility restart.

BECo agreed to make a sample of their EOPs available to the staff in the near future.

II. Direct Torus Vent Modification BECo summarized the details of the direct torus vent (DTV) modification to the staff. The design is ready for field installation. The staff stated that installation of this system would require a Technical Specification change to accomodate an additional containment isolation valve. Additionally the staff stated that, at this time, our review of this modification is ongoing and that we were not prepared to endorse BECo installation or use of this system.

l III. Safety Enhancement Program (SEP)

The staff asked BECo various questions about the SEP and portions of the information package regarding this program, provided to-the NRC on July 8, 1987. The staff stated that review of the SEP is ongoing and that a response to the July 8, 1987 submittal will be provided in the near future.

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• Enclosure 3 August 4, 1987 - Attendees Boston Edison & NRC Emergency Operating Procedures & Torus Vent 1

Name Organization j R. Wessman, Project Manager PDI-3/NRR B. Boger ADRI/NRR T. M. Su RSB/NRR-G. Thomas RSB/NRR John C. Lane SAIB/RES C. Tinkler NRR/SPLB John W. Craig NRC/ PLANT SYSTEMS BRANCH j Robert C. Jones NRC/NRR/SRXB i Jerry Hulman NRC/RES Len Soffer NRC/RES J. J. Persensky NRC/NRR/HFAB W. G. Kennedy NRC/NRR/HFAB V. E.- Barnes BATTELLE/HARC/PNL J. P. Bongarra NRC/NRR/DLPQ/HFAB S. Taggart Rogers OPERATIONS ENGINEERING, INC. ]

R. E. Henry FAUSKE & ASSOC. INC.

J. P. Gerety BOSTON EDIS0N CO.

C.-S. Brennion BOSTON EDIS0N CO. l J. E. Howard BOSTON EDIS0N CO.

V. Nerses NRC/NRR/PDI-3 G. Edgar NAH/B0STON EDISON S. Varga NRC/NRR/DRP/I/II l

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