ML19264B868

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Discusses Possible Resolution of Tech Spec Commitment Re App J of 10CFR50 at Facility.Tech Specs Should Be Modified to Allow Values Not Requiring Tests to Be Valved Out of Sys While Testing During Reactor Operation
ML19264B868
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 03/31/1977
From: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To: Goller K
Office of Nuclear Reactor Regulation
Shared Package
ML093630452 List:
References
NUDOCS 8111040613
Download: ML19264B868 (2)


Text

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3-MAR 311977 Doctet lio.60-247 siL40FJJdAin FOR:

K. R. Galler, Assistant Director for Operating Reactors DDR FR0h:

b. d. Grier, Director, Division of kcacter Inspection Prograus, IE sui 1 JECT:

RESOLUTIOi 0F TECHNICAL SPECIFICATION C0hilTiiENT RElliTIVE To hPPI.NDIX 10F 10 CFR 50 AT INDIAN PT.. Unit h0. 2 The currmt technical stecifications for unit 2 are such as to regaire that the wela channel and pcactration pressurization systen is operable when the reactor is critical (See T-5, 3.3.u, page 2.3-4).

Only portions of this system's pressurized volumes are to be Type B and c testeu while the remining volumes do not noc) to be tested.

The capability exists to valve out the volumes which are not to be leak tasted, but the technical specifications prevent it during operation.

Tne situation has how arisen where the leaLage from total volume pressuri:cd by the weld channel and penetration pressuri:cr. ion system along witn other Type b and C leakage exceecs Appendix o requirments.

This leaves the question of whether the licensee is in cowamancc with the regulation indetermiinable. Without valving out the volumes tudt do n.ot need to be leak tested, it is not possibie to definitely establisn the total Type B ar.d C leakage.

The alternatives appear to be as follous.

1.

Modify the technical specifications to allow the volenes not requiring tests to be valved out of the systtn while testing during reactor operation so tudt a cefinitive test cui be conducted to verify Lu + LC 1 0.5 La.

/.. Require shutdow.. to Wrfuna the tests in urcer tc oect toe current technical specification 3 regaruing cperabi;4ty cf the pressurizatic.a system.

3.

Assce th:,t total leakage of the ccataitcot is.less than L.,

(last Type A test. as 7//bi and Lhot the requiren.nt that

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MAR 311977 the sumation of f and C leakages be less tran 0.G La of Appendix J does not apply.

'n strongly recot.nead tN cancept of the first approach for the fei! wing reesons.

1.

The licensee in response (9/9/75) to your letter of

/w' ust 7,1976 conceraing contaiinent leakage testing 3

indicated that tney would implement the sa:ne requimncats on Unic 2 as were fine.lly agreed on for Unit 3.

Ic that time Unit 3 Technical Specifications were being developed and finalized.

2.

Tne Unit 3 Tachnical Specifications, dated April 5,1976, specifically alloa one header of the pressurization system to be inoperable for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> (See 3.3.D.2).

This would, if implcracnted on Unit 2, allow the test to be performed and a detensination made on whether the leakage is hssociated with 1splation valves or some other co:rponent.

This itsa was brougnt tc the attention of hcadquarters by the region und we are of the opinion the uatter should be resolved within 30 days frow the cate of this menorandu::. He havc enclosed a copy of tne incorning currespondence along with the other relevant documents or extracts.

We will be reaay at your convenience to discuss this itaa and look forward to your response regarding action on the iten.

b. H. Grier, Director Livision of Reactor Inspection Programs Office of Inspection and Enfcrce:aent Enclosarts :

1.

L:stract from T-a for Unit 2 Ltr., Cahill, Coned to Goller, iM, c.

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