BECO-87-127, Rev to 870522 Application for Amend to License DPR-35, Consisting of Amended Fire Protection Tech Specs Pages,In Response to NRC Request at 870617 Meeting

Rev to 870522 Application for Amend to License DPR-35, Consisting of Amended Fire Protection Tech Specs Pages,In Response to NRC Request at 870617 Meeting

ML20236G268
Person / Time
Site:	Pilgrim
Issue date:	07/28/1987
From:	Bird R BOSTON EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20236G271	List: BECO-87-127, Rev to 870522 Application for Amend to License DPR-35, Consisting of Amended Fire Protection Tech Specs Pages,In Response to NRC Request at 870617 Meeting ML20236G282
References
BECO-87-127, NUDOCS 8708040188
Download: ML20236G268 (3)

Text

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A BOSTON EDISON Executive Offices )

800 Boylston Street i Boston, Massachusetts 02199 l

I BECo 87 ~127 Ralph G. Bird Senior Vice President - Nuclear U. S. Nuclear Regulatory Commission 1 Document Control Desk  ;

Washington, D. C. 20555 July 28, 1987 License DPR-35'  !

Docket 50-293 Revisions to the Prooosed Change to Fire Protection Technical Specifications

References:

1) Boston Edison Letter 87-082 dated May 22, 1987, Proposed Change to Fire Protection Technical Specifications.

2) Meeting between Boston Edison Company and NRR Staff on June 17, 1987.

Dear Sir:

Boston Edison Company (BECo) submitted an amendment to Fire Protection technical specifications in Reference 1. Further clarification of certain sections of this submittal was requested by the NRC in Reference 2. The attached pages provide the requested clarifications or explain why clarification is unnecessary. Amended technical specification pages are also attached.

1) Section 3.4/12 " Clarify minimum operable instruments." l J

Sections 3.12A and 4.12A did not identify the " minimum instruments I operable in zone" to correspond to Table 3.12-1. I Sections 3.12A and 4.12A are revised to reflect the " minimum instruments operable in zone" as identified in the last column in Table 3.12-1.

This change is administrative and does not affect the significant hazards consideration included in Reference 1.

A revised page 206 is attached.

2) 4.12.A.2 " Clarify nonsupervised circuitry associated with detector alarms."

A surveillance requirement was proposed for non-supervised fire detection ,

circuitry. The non-supervised circuitry was modified to supervised i 4

circuitry to comply with Appendix A to BTP 9.5-1. He are, therefore, y deleting Section 4.12.A.2 because it is not necessary.

This change is administrative and does not affect the significant hazards consideration included in Reference 1.

U l 8708040188 870728

" OO PDR ADOCK 05000293 i i

P PDR

BOSTON EDISON COMPANY 1

Page 2 '

A revised page 206 is attached.

3. Section 3.12.C.5 " Clarify to indicate that the detectors are included."

The Hydrogen Supply 011 Unit Preaction Sprinkler System is equipped with detectors. The detectors have always been tested during the surveillance tests for the sprinkler systen.. Clarification was needed to incorporate these detectors into technical specifications.

Section 3.12.C.5 is revised to state " Hydrogen Supply 011 Unit Preaction Sprinkler Systems (including detectors)".

This change is administrative. It does not change the significant hazards consideration included in Reference 1.

A revised page 206c is attached.

4) Section 4.12.C.3 " Clarify whether trip testing control is automatic or manual."

It was not clear in the original proposal whether the " trip testing" was automatic or matiual .

The trip testing control for the Preaction Sprinkler Systems is both autoinacic and manua? . In the automatic mode, one of the detectors controlling the preaction valve is actuated to initiate valve opening. In the manual mode a mechanical latch is pulled to open the valve. Trip testing is included in PNPS Procedure 8.B.6, "Preaction/ Deluge Sprinkler System."

No change to the proposed technical specification submittal is required.

5) Section 3.12.0 " Clarify the minimum quantity of Halon required".

The NRC reviewer requested clarification regarding the minimum quantity of Halon required since this was not specified in the existing technical specifications.

The minimum quantity of Halon is 217 lbs. per tank and minimum pressure is 360 psig at 70*F. NFPA 12A, Subsection 1.11.1.6 requires that the tank be refilled or replaced if its net weight declines more than 5%, and if its pressure, adjusted for temperature, drops more than 10%. Proposed technical specification section 3.12.0 states that the Halon system is  ;

operable at 95% of minimum tank weight, and 90% of its pressure. Hence, section 3.120 is consistent with the NFPA requirements.

j No change to the proposed technical specification submittal is required.

I l

l

BOSTON EDIS0N COMPANY Page 3

6) Section 4.12.E.3.c " Clarify to indicate that it is the defective hoses which are to be replaced."

The Section 4.12E.3.c did not specify the type of hoses to be replaced.

Section 4.12.E.3.c is revised into 4.12.E.4.c, and "nontested hoses" is added to indicate that replacement of defective hoses is intended.

This change is administrative, and does not change the significant hazards consideration included in Reference 1.

A revised page 206e is attached.

7) The following administrative changes are made for technical Specification language and numbering consistency.

Page 206e-1 is revised to incorporate an administrative change: section  !

3.12.G.1, " System" is changed to " Systems". Section number 4.12.G.7 is. J added to page 206e-2. These changes are administrative, and do not change the significant hazards consideration included in Reference 1.

1 ch h R. G. Bird l

l Attachmentti Page 206  : Section 3.6/12A I Page 206c  : Section 3.6/12C Page 206e : Section 3.6/12E Page 206e-1: Section 3.4/12G Page 206e-2: Section 3.4/12G c:: R. H. Wessman, Project Manager Division of Reactor Projects I/II Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue ,

Bethesda, MD 20814 U.S. Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Senior NRC Resident Inspector Pilgrim Nuclear Power Station

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