ML19338C962

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Forwards Model Tech Specs for Util Modifying Surveillance Testing Program to Provide Addl Relief & safety-relief Valve Operability & Reliability Assurance
ML19338C962
Person / Time
Site: Dresden, Quad Cities  
Issue date: 08/03/1977
From: Desiree Davis
Office of Nuclear Reactor Regulation
To: Bolger R
COMMONWEALTH EDISON CO.
Shared Package
ML19338C964 List:
References
NUDOCS 8009100995
Download: ML19338C962 (2)


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..c e e t.e s. G% 'd 7 /:0-m AUG 3 1977 and bu-254/60-266 Cow.on.4ealth Edison Company ATT;u Mr. R. L. Bolger Assistant Vice President Post Of fice Sox 767 -

Chicaco, Illinois 60690 Gentie 5:n:

RE:

D^.ESDD: fiUCLEAR POWEft STATION UNIT i;05.1, 2 At:D 3 yet.0-CITIES 1:UCLEAR POWER STATIO!J. WIT NOS.1 At!D 2 In the past several years, a significant number of relief valves cr.d scfety-relief valves were found to be inoperable at EUR react:r facili-ties.

These valves wre installec in the Reactor Coolant Systen and/or Automatic Depressurization Systen. Several prograns hcvc been develened to reduce the incidence of these valve failures; hecover, cdditicr.al failures contir.ue to occur.

Consc ;uently, we have concluded that changes to the Surveillance Require r.ents and Liciting Conditions for Operations for all D:R's are needed to provice additional assurance of relief valve ans safety-rclief valve operability and reliability. Therefore, we reauest that you modify your surveillance testing progran through the adoption of the program contained in the todel ~ technical specifications we have prepared. The cic::ents of this program incluce:

1.

Each remotely operated relief valve and safety-relief valve in the Reactor Coolant Syste ; and Autenatic Ocprcsturizction System will te tested on a vcr able frecueacy schedulc related to i

ce'Onstrated reliability and operchility. The testi:n, inttrval is casoc on the nurner of vc1ve failurcs curinn the recaire:2 tast i r.terv al. Facilities with reliable valves vill progreds to a Icn Nr test interval while tocce witn volve failurcs uill procrest te t snorter test int rval.

This concept should result in tite :uir,tanc.we of a ecre unifem icvel of reliability for this equipr.:ent than creviously cbtainea.

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l Comonsealth Edison Ccapany 4UL j

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Th *: increar.cd surveillance program v.ill becoac ch ect.ip en iurch 1,

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'1979.

No increase in valve testing is required before that date.

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The initici testing interval of the increased surveillance procrcu will be based on the nu.iber of remotely operated relicf valves ane j

safety-relief valvcs found inoperable in the previous 10 months i

(5eptenber 1,1977 to harch 1,1979)..This lecc tirc will perai t the resolution of the hark I Safety-T.elief Yalve loads and Structural Capability cencric concern. Additionally, this lead tic:e is sufficient to pennit the develora.ent and imple.7entation of ir. groved safety and safety-relief valve raaintenance procecures anc other corrective actions prior to implementing the test program.

3.

The relief and/or safety-relief valve line restraints in the tores will te exa":ined prior to initiating the test croprc? end at 1 cast once each fuel cycle (i.c., each 18 montns) to verity continvec structural Integrity.

We request that you submit within 30 days froa your receipt of this letter, an application for amen &ient to your license that will change your technical spt.cifications to be in ccaformance with the requirements of the enclosed r.odel technical specifications and associated bases.

In the event you should desire further discussion of this matter, please contzct us.

Sincerely,

% 6nal N ned by i

R Don K. Davis, Acting Chicf Operating Reactors Branch d2 Division of Operating Recctors Er: closure:

DISTRIBUTION:

Jodel Technical Docket (5)

ACRS (16)

Specifications f1RC PDR (5) local PDR (2) cc a/enclnsurc:

ORB-2 Reading RBevan Sea ne.v.t pana.

PHO Connor RMDiggs JWetmore TJCarter DEisenhut Attorney, OELD I&E(3)

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