ML20245C319

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Provides Addl Info Re Suitability of Seal Matl Installed in 36 Bergen Patterson Hydraulic Snubbers on Reactor Coolant Pump/Steam Generator Cubicles.Matl Determined as Having Been Demonstrated as Compatible W/Environ in Which Installed
ML20245C319
Person / Time
Site: Beaver Valley
Issue date: 03/31/1978
From: Dunn C
DUQUESNE LIGHT CO.
To: Schwencer A
Office of Nuclear Reactor Regulation
References
NUDOCS 8710260098
Download: ML20245C319 (3)


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(4 t 2) 4714300 C.: L.xu /. venue f#1'tEl'Uf)h, r0fif tSylv Ard(1 15?!O March 31, 1978 L

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o Director of Nuclear Reactor Regulation

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United States Nuclear Regulatory Cct:nission

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Attention:

Mr. A.

Sclnienc e r, Chief 7-re 7,

Operating Reactor:, Branch Wo. 1 ci g

Division at Operating Reactors Washington, D. C.

20555 Re f e renc e :

Beaver Valley Pouer Station, Uni t. No. 1 Docket No. 50-334 Request for llydraulic Snubber Seal Material 1' valuation Gentlemen:

1:nclot od is additional informa tion relating to the suitability of the seal raaterial installed in the thirty-six (36) Dergen Patterson liydraulic Snubbers on the No. I linit.

These t hir ty-nl: (36) snubbera are installed in the Reactor Coolant Pump / Steam Generator Cubicles.

There are four (4) snubbers on each of the following.

(a)

Steam Generator Supports (b) henctor Coo:lant Pump Supports (c)

Upper Sten:a Generator Shell The maxiuuni radiat ion field t o which t hese snubberr will be exposed is 22,000 M. nomma and 900 [E neutron.

(Figure 4.1-6 of AtLachment 1.)

or ar The neal mate rials have been de t en tined to be suitable for nervice at t erapera t.urus up to 13?l' (At t ac hme n t 3) and fluences of 107 rads ( A t t a c ?:ne a t /, ).

Thc nanin.um ope rat ing t empt rat ure of the snubbers is expected to be icen t han.10P I' (Attachment 2).

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9 Iscaver Valley Power Station, Unit I;o. 1 Dock'et I:o. 50-334 lleq ues t for liydraulic Snubber Seal Material Evalantion l

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The gu:ned millable polyurethane scaln presently installed as static seals will be replaced no less frequent.ly than once in ten years in accordance with the existing station maintenance program.

This will ausure that the 1.iaximum attainable fluence will be less than f

2.5 x 10> rada.

This provides a safety factor of 4.

j 13ased upon this evaluation, we believe that this material should be determined as having been denonst rated as con:patible with environment in which it is installed.

This determination will enable us to comply with the surveillance requirements of Appendix A, Technical Specification 4.7.8.12.1'instead of the requirements of Technical Specification 4.7.8.12.2 which presently require nn unnecessary plant shutdown every thirty (30) days.

If you have nny questions concerning this response, please contact my office.

1 Very truly yours,

. VI Lh<o~

C. N.# Dunn Vice President, Operations Attachments e

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CATE OF OOCUMENT

.i Mr. A. Schwencer Duquesne Light 03/31/78 i

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Pittsburgh, PA 15219 oATc sectivro C. N. Dunn 04/03/78

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