ML20126J309

Responds to IE Bulletin 80-25, Operating Problems W/Target Rock Safety-Relief Valves at Bwrs. Safety-relief Valve Pneumatic Supply Sys Reviewed & Potential for Overpressure Situation Found Negligible

ML20126J309
Person / Time
Site:	Peach Bottom
Issue date:	03/18/1981
From:	Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
IEB-80-25, NUDOCS 8104240314
Download: ML20126J309 (6)

Text

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PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET f.

g P.O. BOX 8699. '

N q k 1881 1981 PHILADELPHI A. PA.19101

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( 15) 8 5MI SHIELDS L. DALTROFF 7

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March 13, 1981 ml@

Docket Nos. 50-277 50-278 IE Eulletin 80-25 Mr. Boyce H.

Grier, Director Region 1 Office of Insocction & Enforcecent US Nuclear Re gula tory Co:mi s sion 631 Park Avenue King of Prussia, PA 19406

Dear Mr. Grier:

This letter is in response to your letter, which forwarded IE Bulletin 80-25.

" Actions to be taken by utilities with B '19 plants" are restated below with our responses.

In response to your request concerning nannower requirements, aporoximately 55 nanhours were expended in preparing this resnonse.

Actions to be Taken by Utilities with %'R plants uith O p e r a t i n :;

Licenses or Near-Tern Operating Licenses:

1.

If your facility has not yet installed or changed or is presently in the process of changing to the two-stage S/R valves, initiate appropriate quality control nrocedures to assure inspection of the solenoid actuators for excess Loc-tite prior to operation.

If the solenoid actuator nanufactured by Target Rock Corporation is already installed in your facility, confirm its operability either by its operational nerformance (i.e.,

it has functioned as designed following an aging period of about 3 nonths in the higher tenperature environnent of power operating conditions) or by functional testing at full pressure during the next refueling THIS DOCUMENT CONTAINS P00R QUAUTY PAGES 8104240314

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Mr..Boyce Grier Page 2 shutdown of the. facility.

Include in your report the results of'all attempts to operate the.two-stage S/R valve (s).

Resnonse 1h3 two stage safety / relief valves (SRV's) a r,e currently installed at' Peach Bottom, nor are there any plans to install them at this time.

2.

In the event that a S/R valve, regardless of make or model (e.g.,

both two or three stage), fails to function as designed, excepting for pressure setpoint requirements, and the cause of the malfunction is not' clearly determined, understood, and therefore corrected, standard operating procedures shall require that the entire valve be removed from service, disassembled, inspected, adjusted, and pressure setpoint tested with steam for proper operation prior to returning the valve to service.

These overhaul requirements shall be at least equivalent to those applicable to periodic surveillance rehabilitation requirements.

Appropriate revisions to your operating procedures shall be made to include these requirements.

Response

Procedure OT-35 " Inadvertent opening of Safety / Relief Valve" and CP-2A Check Off List'" Reactor Startup Order" are being modified to include steps regarding malfunctioning safety / relief valves.

3.

A review of your S/R valve pneunatic supply systems shall be performed to determine the potential for and ma r,n i t u d e of an overpressure condition.

The determined overpressure potential of the pneumatic supply shall he compared with the naximum operating pressure capabilities of the solenoid actuator valves serving the S/R valves, so as to determine whether supoly pressure could result in valve malfunction.

Protective devices (such as relief valves) shall ne installed in the proxinity of the S/" valves and set to protect against supply pressure in excess of the enerating pressure capabilities of the solenoid actuator device.

In addition, consideration should be given to nodification or'renlacenent to reduce the sensitivity of the solenoid actuat,or to pneunatic supply overpressure.

Further, the f a i'l u r e, either high or low, of the pneumatic supply system shal- 'bo annunciated to the control roon operator.

The a r..n u n c i a t e d sunply pressure shall be measured at

a. location ta close as practical to the S/7 valves and downstrcan of any check valve connecting two or more pneumatic sourcer.

Apnropriate operating procedures shall be provided to guide orerator w

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Mr.;Boyce Grier' Page 3 response to.such an occurrence of high or lou supply pressure.

Response

We have completed a review of the S/R valve pneumatic supply systems at' Peach Bottom and;have concluded that the potential for an overpressure situation, as described, is negligible.

A basis

.for our deternination is as follows:

a)

The pneunatic supply to the S/R valves is from the Instrument Nitrogen System (P&ID M-333).

This systen consists of two trains of instrunent air compressors, filters, dryers, receiver tanks, which take suction fron the drywell atmosphere and provide compressed gas at a pressure of 85-105 psig to the A and B drywell instrunent headers.

In addition, the five S/R valves utilized for the Automatic Depressurization System (ADS) ara provided with accumulators.

b)

Low pressure in the Instrunent Mitrogen System receiver tanks is annunciated in the control room and station Instrument Air i

is provided as a backup.

Operators have an annunciator alarm card which provides direction in the event of this alarn.

High pressure in either Instrument Air System is prevented by compressor control logic and multiple relief valves, c)

Under current design, no source of high pressure gas or liquified gas is utilized in the S/R valves pneumatic supplies.

A system is under design which will provide a long term safety grade pneumatic supply to the SRV's associated i

with ADS.

The new systen, which is to be used only as a backup, has as a source the Containment Atmosphere Dilution (CAD) nitrogen facility which consists of a liquid nitrogen tank, vanorizers, and associated instruments and controls.

Provi sions for overpressure protection / relief of this system will be made downstrean of all pressure res,ulating devices and external to n rima ry containnent.

Ancropriate control room indication will be provided to identify low system I

pressure.

d)

The Target Rock SRV's in use at Peach Botton are equipped with three stage top-works and Automctic Valve Company (AVCO) solenoid valves.

As stated in IE Information Nutice 80-40, these solenoid valves have been tes ted to 300 osi; and found not to leak.

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a Mr. Boyce Grier.

'Page 4 Since the review described above clearly-indicates that thej-problems described'in IE Information Notice 30-40 and It

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Bulletin 80-25 are not applicab1'e to the Peach Bottom SRV pneumatic.sunply systems, no plans are being made f or any systen modifications in response to-this concern.

Very truly yours,

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L Atts.chment u

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cc:

Victor.Stello, Director Office of Inspection & Enforcement US Nuclear Regulatory Commission Washington, DC 20555

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!COMM014WCALTH'0FJPENNSYLVANIA :

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-COUNTY OT PHILADELPilIA

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L.-Daltroff, being.first duly sworn, deposes-and says:

That he is Vice President of Philadelphia Electric Company; that.he has read the foregoing response to IE Ilul le t in t

80-25 and knows the contents thereof; and that the statements and matters set forth therein a re true'and' correct to the best of his i

knowledge, information and belief.

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Subscribed and sworn to before me this l day of dA b

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UZASETH H. BOYER Nota. Public, Phila., Phita. C.

. ission Expires Jan. e,1982 l

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