ML19332A833

Application for Proposed Change 91 to Tech Specs in Response to TMI Lessons Learned Category a Items.Revises Tables 3.2.6 & 4.2.6 to Incorporate Instrumentation Monitoring Requirements & Table 6.1.1 Re Shift Technical Advisor

ML19332A833
Person / Time
Site:	Vermont Yankee
Issue date:	09/12/1980
From:	Heider L VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML19332A834	List: ML19332A833 ML19332A835
References
RTR-NUREG-0578, RTR-NUREG-578 WVY-80-131, NUDOCS 8009180451
Download: ML19332A833 (3)

Text

Propou d Chrnge #91 s

i VERMONT Y AN KEE NUCLEAR POWER CORPOR ATION SEVENTY SEVEN GROVE STREET RUTLAND, VERMONT 05701 B.3.2.1 REPLY TO'.

7 ENGINEERING OFFICE h# TURNPIKE RO AD WEST 80RO M ASS ACHUSETTS 01581 TELEPHONE 617-366-9051 September 12, 1980 United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Office of Nuclear Reactor Regulation l l

References:

(a) License No. DPR-28 (Docket No. 50-271)

(b) USNRC Letter to All Boiling Water Reactor Licensees dated July 2,1980

Subject:

Technical Specifications for TMI Lessons Learned Category "A" Items

Dear Sir:

Pursuant to Section 50 59 of the Commission's Rules and Regulations, l

Vermont Yankee Nuclear Power Corporation hereby proposes the following changes to the Technical Specifications. l l

PROPOSED CHANGE:

- Tables 3 2.6 and 4.2.6 are revised to incorporate conditions for operation and surveillance requirements for safety and relief valve position monitoring instrumentation.

Table 6.1.1 is revised to include the Shift Technical Advisor (STA) in the minimum shift crew composition. Section 6.1 is revised to specify the minimum qualification requirements for the STA.

REASON FOR CHANGE:

Reference (b) transmitted model standard technical specifications which were intended to provide guidance in the scope and types of specifications required to assure that facility operation is maintained within acceptable limits following implementation of the TMI-l Lessons Learned Category "A" items.

Using the NRC's model technical specifications as guidance, we have determined that certain revisions to Vermont Yankee Technical Specifications are appropriate. These revisions are identified above and in the attached technical specification pages.

1 8009180 Y /

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United States Nuclear Regulatory Commission September 12, 1980 Attention: Office of Nuclear Reactor Regulation Page 2 BASIS FOR CHANGE:

The addition of valve position indication instrumentation requirements to the technical specifications will provide reasonable assurance that the system will be available as a diagnostic aid to the operator when required. It is the opinion of the licensee that this indication is an operator aid and is not related to the safe operation of the plant. Therefore, limiting conditions for operation are not necessary.

Changes are proposed to specify minimum STA qualifications and requirements to ensure that a knowledgeable individual is available to enhance the plant operating staff's capabilities for responding to off-normal conditons and for evaluating operating experience.

SAFETY CONSIDERATIONS:

The safety and safety / relief valve position monitoring systems were installed at Vermont Yankee in February,1980. It was concluded that the changes did not present significant hazards not described or implicit in the safety analysis report, and did not involve an unreviewed safety question as described in 10CFR50 59 The proposed technical specifications will ensure that appropriate equipment and administrative requirements are applied.

Incorporation of STA qualifications and requirements is administrative in nature.

This change has been reviewed by the Vermont Yankee Nuclear Safety and Audit Review Committee.

FEE DETERMINATION:

This proposed change requires an approval that involves a single safety issue and is deemed not to involve a significant hazards consideration. For these reasons, Vermont Yankee Nuclear Power Corporation proposes this change as a Class III Amendment. A payment of $4,000.00 is enclosed.

SCHEDULE OF CHANGE:

Tables 3 2.6 and 4.2.6 changes described above will be incorporated into the Vermont Yankee Technical Specifications upon receipt of your approval.

Section 6.1 and Table 6.1.1 changes described above will be incorporated into the Vermont Yankee Technical Specifications upon completion of the Shift Technical Advisor Training Program (expected during May or June, 1981), and receipt of your approval.

Unitsd States Nuclear Regulatory Commission September 12, 1980 4 Attention: Office of Nuclear Reactor Regulation Page 3 We trust you will find this information satisfactory; however, should you desire additional information, feel free to contact us.

Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION Y

L. H. Heider Vice President COMMONWEALTH OF MASSACHUSETTS) l- )ss COUNTY OF WORCESTER )

i l Then personally appeared before me, L. H. Heider, who, being duly sworn, did state that he is a Vice President of Vermont Yankee Nuclear Power Corporation, that he is duly authorized to execute and file the foregoing l request in the name and on the behalf of Vermont Yankee Nuclear Power Corporation, and that the statements therein are true to the best of his knowledge and belief.

.d l***** Robert H. Groce Notary Public

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()pe rahle in t itunent M ge I hmnie 1:. Paramet er Type of Indicat ion Drywell Atmospheric Temperature llecorder Il16-19-45 0 .ROUF 2

Itecorder flTit 149 0-300i?

(Note 1) i Drywel1 Pressure (flote 1) Iteconfer Il16-19-44 0-80 psia 2

0-80 psia l

Torus Pressure (Note 1) 2 Tonis Water I.evel (Note 3) tkiter lil6-19-46A 0-3 ft.

Meter 1116-19-4611 0-3 ft.

7 Torus Water Temperature Meter # 16-19-48 60-1800F (Note 1)

Itecorder fl6-97 0-1200 psig 2 Iteactor Pressure (Note 1) U-l/00 psig Iktt er ll6-90A Meter lib-90lt 0-1200 psig 2 Iteactor Vessel Water I.evel Meter ll2-3-91A (-150)-0-(+150)"l! 20 (tJote 1) Meter # 2-3-9111 (- 150) (+ 150 )"1120 Control Itod Position (tJote 1,2) Meter 0-48" ItPIS 1 .

ticut ron f4)ni t or (Not e 1,2) Meter 0-125% ltated Flux I .

!!cconter #16-19-45 0-30001-

-- - I ---_ To rus _ Ai_r__Temnera t ure (Not e_1) ,

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NA Safety / Relief Valve Position from pressure switches 1ights (SFV 2-71-A through D) Closed - Open NA Sa f e ty Va lve Pouition from Accoustic Monitor Meter ZI-2-1A/11 Closed - Open 49