ML19247B760

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Requests Proposed Change 69 to App a of License DPR-36 Re Composition & Organization of Onsite Fire Brigade.Revised Tech Specs Encl
ML19247B760
Person / Time
Site: Maine Yankee
Issue date: 08/07/1979
From: Vandenburgh D
Maine Yankee
To: Reid R
Office of Nuclear Reactor Regulation
Shared Package
ML19247B761 List:
References
WMY-79-77, NUDOCS 7908130457
Download: ML19247B760 (2)


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PC #69-1 B.3.F.1 August 7, 1979 WMY '.9-77 United States Nuclear Regulatory Commission Washington, D.C.

20555 Attention: Office of Nuclear Reactor Regulation Robert W. Said, Chief Operating Reactors Branch #4 Division of Operating Reactors

References:

(a) License No. DPR-36 (Docket No. 50-309)

(b) USNRC letter from K. R. Goller to F..

H. Groce, dated November 25, 1977;

Subject:

Fire Protection Technical Specifications (c) MYADS letter (WMY 77-114) to ONRR dated December 14, 1977;

Subject:

Fire Protection (d) USNRC letter from R. W. Reid to R. H. Groce dated February 2, 1978;

Subject:

Amendment No. 35 to Facility Operating License

Dear Sir:

Subject:

Maine Yankee Fire Protection Technical Specifications Pursuant to Section 50.59 of the Commission's Rules and Regulations, Maine Yankee Atomic Power Company hereby proposes the following modification to Appendix A of the Operating License.

Proposed Change:

Reference is made to the Operating License DPR-36 and the Technical Specifications contained in Appendix A issued to the Maine Yankee Atomic Power Company for the Maine Yankee Atomic Power Station.

We propose to make the following change:

1.

Page 5-1, Section 5.2.2f Change the first sentence to:

"A fire brigade of at least 5 members shall be maintained onsite at all times."

Revised page 5-1 is provided as enclosure.

Reason for Change: The proposed change is in direct response to the USNRC's demand that the Maine Yankee Atomic Power Cc=pany amend Maine Yankee's Operating License.

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.. United States Nuclear Regulatory Commission Page 2 August 7, 1979 Bases for Change: The proposed change addresses the issue of fire brigade size put forth in the draft Fire Protection Technical Specifications included in Reference (b) above, and is intended to comply with the NRC concerns expressed in that reference and in various other documents, meetings, and telephone conversations.

Safety Considerations: The change proposed has been requested by the NRC and is not considered to constitute an unreviewed safety question. This change has been reviewed by the Nuclear Safety Audit and Review Committee.

Fee Determination: The Commission has determined that no license amendment fee is required to accompany applications or requests to incorporate NRC-recommended Technical Specifications for Fire Protec tion. This Proposed Change meets that criterion, thus no fee is included.

Schedule of Change: This change will be incorporated into Maine Yankee's Technical Specifications 90 days after approval by the Commission. This schedule will allow sufficient time to qualify those individuals who will additionally be designated as fire brigade members, in current fire fighting practice and plant fire fighting procedures.

We trust that this information is acceptable to you; however, should you have any questions, please contact us.

Very truly yours, MAINE YANKEE ATOMIC POWER COMPANY MV D. E. Vandenburgn Vice President EAS/DEWdep Enclosure COMMONWEALTH OF MASSACHUSETTS)

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COUNTY OF WORCESTER

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When personnally appeared before me, D. E. Vandenburgh, who being duly sworn, did state that he is Vice President of Maine Yankee Atotric Power Company, that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Maine Yankee Atomic Power Company, and that the statements therein are true to the best of his knowledge and belief.

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M R. H. Groce Notary Public f..~(

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United States Nuclear Regulatory Commission Page 3 August 7, 1979 5.0 ADMINISTRATIVE CONTROLS 5.1 RESPONSIBILITY 5.1.1 The Plant Superintendent shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.

5.2 ORGANIZATION OFFSITE 5.2.1 The offsite organization for facility management and technical support shall be shown on Figure 5.2-1.

FACILITY STAFF 5.2.2 The Facility organization shall be shown on Figure 5.2 2 and:

a.

Each on duty shift shall be composed of au least the minimum shift crew composition shown in Table 5.2-1.

b.

At least one licensed Operator shal] be in the control room when fuel is in the reactor, c.

At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery from reactor trips.

d.

An individual qualified in radiation protecticn procedures shall be on site when fuel is in the reactor.

ALL CORE ALTERATIONS shall be directly supervised by either a e.

licensed Senior Reactor Oparator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

f.

A fire brigade of at least 5 members shall be maintained onsite at all times. This excludes 2 members of the minimum shift crew necessary for the safe shutdown of the plant and any personnel required for other essential functions during a fire emergency.

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