ML20209D826

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Forwards Application for Amend to License DPR-66,consisting of Rev 2 to Proposed Tech Specs Change Request 126 to Reflect Design of Control Room Emergency Habitability Sys
ML20209D826
Person / Time
Site: Beaver Valley
Issue date: 04/16/1987
From: Carey J
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20209D831 List:
References
2NRC-7-086, 2NRC-7-86, ND1NSM:2647, NUDOCS 8704290370
Download: ML20209D826 (3)


Text

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'Af I p one (412)393-6000 Nuclear Group NDINSM:2647 P.O. Ba 4 Shippingport, PA 15077-0004 U.

S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, DC 20555 l

Reference:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Proposed Technical Specification Change Request No. 126 Revision 2 Gentlemen:

On April 2,

1987, we presented details of the Beaver Valley combined control room emergency habitability systems to the NRC Staff.

This meeting was a result of questions regarding the design of the emergency habitability systems and the corresponding Technical Specification changes previously submitted.

Also, at the NRC reviewers
request, from an earlier conversation, we developed a common Technical Specification for both Unit No. 1 and No. 2 and presented the details and philosophy of operation to the Staff.

The design of the control room emergency habitability systems as they protect the combined control rooms was found acceptable by the NRC Staff and subsequently, the combined control room habitability system Technical Specifications were reviewed and agreed upon in concept by the NRC Staff.

As a result of this meeting we have prepared Revision 2

to Technical Specification Change Request No. 126 which is attached herewith for your review.

Enclosed are:

A.

One (1) original and thirty-seven (37) copies of an Application for Amendment to our Operating License to revise our previous submittal of Specification 3/4.7.7 and 3/4.9.15 CONTROL ROOM EMERGENCY HABITABILITY SYSTEMS by:

1.

Requiring operability of two out of three available control room emergency ventilation subsystems, and five bottled air pressurization subsystems.

2.

Requiring that control room ventilation system normal air intake and exhaust isolation dampers are operable and capable of automatic closure on a

containment isolation, control room high radiation, and chlorine isolation signal, or closed.

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1 Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Proposed Operating License Change Request No. 126, Revision 2 Page 2 3.

Expanding the applicability statement to include periods of time when either unit is in modes 1, 2, 3 or 4,

when moving irradiated fuel at either unit, and to reference Specification 3.9.15 for requirements applicable when both units are in either mode 5 or 6.

4.

Dividing surveillance requirements into two separate requirements for demonstrating operability of the BVPS-1 and BVPS-2 emergency ventilation subsystems.

5.

Expanding surveillance requirement 4.7.7.2b to include verification that a) a

chlorine, control room high radiation or CIB test signal from either unit will initiate bottled air pressurization system operation, and b) the bottled air pressurization system is operable by performing a partial discharge test.

These changes have been reviewed by the OSC and ORC and have been determined to be safe and do not involve an unreviewed safety question.

B.

Thirty-eight (38) copies of documents designated Attachments A

and B

which setforth the change in Technical Specifica-tions and its no significant hazards evaluation.

Statements in the No Significant Hazards Evaluation (Attachment B of this letter) regarding the limiting accident with respect to control room operator dose, and worst case chlorine concentration in the control room following an on-site chlorine release were made pending confirmation of accident analysis results.

The statements to be confirmed include:

1) A small line break outside of containment at Unit 2

is the limiting accident with respect to operator dose in the control room in meeting GDC-19.

2)

For an onsite chlorine release accident, the chlorine concentration in the control room will not exceed 15 ppm by volume (45 mg/m ) within 2 minutes after the 8

operators are made aware of the presence of chlorine.

We expect to obtain the analysis results and forward notification that these statements are confirmed as stated by Friday, May 8, 1987.

This is a

revision to an amendment request for which an application fee has been provided pursuant to 10 CFR 170, therefore, we have determined that no additional application fee is required.

Very tr 1

yours,

/

J. J. Carey Senior Vice President, I

Nuclear Group Attachments

p Bnaver Valley Power Station, Unit No. 1 Docket No. 50-334, Licenso No. DPR-66 Proposed Operating License Change Request No. 126, Revision 2 Page 3 I

cc: Mr. W. M. Troskoski, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission Regional Administrator Region 1 631 Park Avenue King of Prussia, PA 19406 Mr. Peter S. Tam U. S. Nuclear Regulatory Commission Project Directorate No. 2 Division of PWR Licensing - A Washington, DC 20555

- Mail Stop 316 Addressee only Director, Safety Evaluation & Control Virginia Electric & Power Company P.O. Box 26666 l

One James River Plaza Richmond, VA 23261 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection Pennsylvania Dept. of Environmental Resources P.O. Box 2063 Harrisburg, PA 17120 s,

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