ML20129E230

Requests Assistance in Conducting Review of Encl Util 850423 Submittal Re Containment Isolation Valves Under Administrative Control.Safety Evaluation & SALP Input Expected by 850831

ML20129E230
Person / Time
Site:	Maine Yankee
Issue date:	05/24/1985
From:	Thompson H Office of Nuclear Reactor Regulation
To:	Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
TAC-57635, NUDOCS 8506060393
Download: ML20129E230 (3)

Text

.. .

May 24, 1985 MEMORANDUM FOR: Richard W. Starostecki, Director Division of Reactor Projects

, Region I FROM: Hugh L. Thompson, Jr., Director Division of Licensing

SUBJECT:

CONTAINMENT ISOLATION VALVES UNDER ADMINISTRATIVE CONTROL Your assistance is requested in conducting a review of the enclosed submittal from Maine. Yankee Atomic Power Company dated April 23, 1985. The product expected as a result of your review is a completed safety evaluation. Your reviewers should use the Standard Review Plan (SRP) and Standard. Technical Specifications (STS) as guidance in determining acceptance criteria, recog-nizing, of course, that, for operating reactors, the criteria in these documents are not requirements.

In accordance with NRR Office Letter No. 44, each safety evaluation performed-by a technical division shall have a separate SALP input provided. For pur-poses of these reviews, the Regional personnel involved are considered part of the technical divisions. Therefore we are requesting that your forwarding memorandum contain a SALP input for each safety evaluation performed.

Work for this review effort should be charged under TAC 57635. The requested completion date is August 31, 1985. Please notify me as soon as possible if this completfo.. date is acceptable. Any contact with the licensee on this review effort or any additional information deemed necessary should be obtained through the NRR project manager. The project manager for this plant is P. Seart and he can be reached at 492-7458 (FTS).

Origina! Signed by Hugh L Thompson, Jr.

Hugh L. Thompson, Jr., Director Division of Licensing

Enclosure:

DISTRIBUTION:

As stated N ORB #3 RDG cc w/ enclosure NRC PDR J. Thoma ORB #3 RDG D. Haverkamp PMKreutzer K. Heitner KHeitner P. Sears PSears HLThompson GClainas CONTACT:

P. Sears X27458 *See previous concurrence page ORB #3:DL* ORB #3:DL* ORB #3:DL*

EGTourigny AD:0R*

GClainas D:DL-ff HThompson PKreutzer PSears:dd 5/20/85 5/20/85 5/20/85 5/20/85 7733/85 8506060393 850524 PDR ADOCK 05000309 P PDR

, May 24, 1985

-MEMORANDUM FOR:: Richard W. Starostecki, Director-Division of Project and Resident Pro 3 rams, Region-I FROM: Hugh L. -Thompson, Jr., Director Division of Licensing I

SUBJECT:

- CONTAINMENT. ISOLATION VALVES UNDER ADMINISTRATIVE CONTROL

.Your assistance is requested in conducting a review of the enclosed submittal

-from Maine Yankee Atomic Power Company dated April 23, 1985. The product expected as a result of your review is a completed. safety evaluation. Your reviewers should use the Standard Review Plan (SRP) and Standard Technical Specifications .(STS) as guidance in determining acceptance criteria, recog-nizing, of course, that, for operating reactors, the criteria in these

. documents:are not-requirements.

In accordance with NRR Office Letter No. 44, each safety evaluation performed by a technical division shall have a separate SALP input provided. For pur-poses of these reviews, the Regional personnel involved are corsidered part of the technical divisions. Therefore we are requesting that ycar forwarding memorandum contain a SALP input for each safety evaluation performed.

Work for this review effort.should be charged under TAC 57635. The requested completion date is August 31, 1985. Please notify me as soon as possible if-this completion date is acceptable. Any contact with the licensee on.this

. review effort or any. additional information deemed necessary should be obtained through the NRR project manager. The project manager for this plant is P.' Sears and he can be reached at 492-7458 (FTS).

- Hugh L. Thompson, Jr., Director -

Division of Licensing

Enclosure:

DISTRIBUTION:

As stated DOCKET FILE ORB #3 RDG cc w/ enclosure NRC PDR J. Thoma ORB #3 RDG D. Haverkamp' PMKreutzer K. Heitner KHeitner P. Sears PSears HLThompson GClainas

. CONTACT:

.P. Sears X27458 0R8f::DL kM 0RB#3:DL'

/34' #/

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' MNRE a SARHEE , M0ml0 POWERCOMPARU e suaugr,Tl,?n",y, Y """"# April 23, 1985 (207) 623-3521 Proposed Change #114 jg MN-85-76 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D. C. 20555 1

Attention: Document Control Desk

References:

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

(b) MYAPCo Letter USMC dated March 15, 1985 (MN-85-56)

Schedule for Submittal of Post Accident Sampling Technical Specifications (c) USNRC Letter to MYAPCo dated April 11, 1985 Post Accident Sampling Technical Specifications for Procedures

Subject:

Containment Isolation Vavles Under Administrative Control Gentlemen:

In Reference (b) above, Maine Yankee agreed to submit proposed changes to our Technical Specifications addressing sampling and analyis of primary coolant and containment atmosphere under post accident conditions. Following discussions with your Staff and receipt of Reference (c), Maine Yankee has concluded that it is preferable to address post accident sampling in our Emergency Operating Procedures rather that in Technical Specifications.

. However, in order to adequately test portions of the post accident sampling system, it is necessary to propose changes to our Technical Specifications permitting realignment of certain containment isolation valves.

Therefore, pursuant to the Commission's Rule and Regulations (10 CFR 10.90), Maine Yankee requests that Appendix A of our Operating License be amended as follows:

Remove existing page 3.11-2 and replace with new page 3.11-2.

This change to Section 3.11 adds to the list of manual containment isolation valves which may be reoositioned under administrative control without taking specific compensatory measures. This will permit flow testing of post accident hydrogen purge and analysis system, as well as obtaining containment atmosphere samples for analysis.

Each of these new valves is in a small bore line and would t'e opened only briefly for the purpose of demonstrating flow or obtaining a samole. Hence, the probability of an accident occurring during the time the valve are open is small. g 29

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MAINE YANKEE ATOMIC POWER COMPANY United States Nuclear Regulatory Commission Page Two Attention: Document Control Desk MN-85-76 We have,'therefore, concluded that this proposed change would not significantly increase the consequences of a previously analyzed accident nor wculd it increase the probability of an accident occurring. Neither does this change create the possibility of a previously unanalyzed accident. Hence no significant hazards considerations are involved.

This change has been reviewed and approved by the Plant Operation Review Committee. As well, the Nuclear Safety and Audit Review Committee has reviewed this proposed change.

A representative of the State of Maine is being informed of this change request by a copy of this letter.

Enclosed is our check for $150.00 to cover the application fee for this proposed change.

Very truly yours, MAINE YANKEE ATOMIC POWER COWANY

~

John. B. Randazza Executive Vice President FWS/bjp

Enclosure:

cc: Mr. James R. Miller Dr. Thomas E. Murley Mr. Cornelius F. Holden

< Mr. Clough Tappan STATE OF MAINE )

)ss COUNTY OF LINCOLN )

Then personally appeared before me, Sohn B. Randazza, who being duly sworn did state that he is Executive Vice President of Maine Yankee Atomic Power Company, that he is duly authorized to execute and file the foregoing request in the name and on behalf of Maine Yankee Atomic Power Company, and that the statements therein are true to the best of his knowledge and belief.

hWNotary Public uy c::. :.I $lx = s oticN 19.1991

. MAINE YANKEE ATOMIC POWER COMPANY

~ Exception:

1. Manual containment isolation valves may be repositioned under the administrative controls provided prior compensatory measures are taken to isolate the penetration. Compensatory measures which may be taken include closing other valves or installing blind flanges to isolate a penetration. Compensatory measures which are in effect for longer than seventy-two hours must meet the same design criteria as the original containment isolation valve.

2. The following manual containment isolation valves may be repositioned under administrative control without compensatory measures to isolste the penetration: ,

RH-4, 6, 7, 26 MS-48, 50, 68, 70, 88, 90, 239, 241, 243 PAP-1, 4, 23, 24, 25 ]

HPD-4, 5, 9, 10, 14, 15 1A-212, 213, 218, 219, 220 ]

Remedial Action:

With one or more automatic or remotely operated containment isolation valves inoperable, maintain at least one automatic or remotely operated isolation valve operable in each affected penetration that is open, and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:

1. Restore the inoperable valve to operable status, or

2. Isolate the affected penetration by use of at least one manual, remotely operated or deactivated automatic isolation valve secured (tagged) in the closed position or by use of a blind flange.

Ccmpensatory measures which are in effect for longer than seventy-two hours must meet the same design criteria as the original containment integrity valve.

C. The reactor shall not be critical if the containment internal pressure exceeds 3 psig.

D. On-line containment purge.

On-line purging of containment is not allowed under the conditions of Specification 3.ll.B above, unless the following conditions are satisfied:

1. Prior to the depressurization of the containment for on-line purge, the two purge supply, two exhaust valves and one exhaust bypass valve will be cycled to test the automatic closure feature using both the Containment Gaseou: Activity and Primary Vent Stack Gaseous Activity closure signals. The operation of the inner and outer supply and exhaust 8504300305 850423 PDR ADOCK 05000309 P PDR 3.11-2 04/22/85 5344L-FWS