ML20086L219

AO 74-17:on 740329,indication of Bellows Leak Found on Reactor Relief Valve 71G.Cause Unknown.Corrective Action Will Be Undertaken Following Next Shutdown

ML20086L219
Person / Time
Site:	Peach Bottom
Issue date:	04/05/1974
From:	Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Giambusso A US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20086L221	List: ML20086L219 ML20086L223
References
AO-74-17, NUDOCS 8402070465
Download: ML20086L219 (2)

Text

-- _

~

. O O PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET _g PHILADELPHIA PA.19101 sais 841-400o P-

,-l is , y :." p#

t,L{';# ,

l April 5,1974 {W> j[$,6,./

e

)f Mr. A. Giambusso Deputy Director of Reactor Projects United States Atomic Energy Commission l Directorate of Licensing j Washington, D.C. 20545 ,

1

Subject:

Abnormal Occurrence The following occurrence was reported to Mr. R. A. Feil, A.E.C. Region I Regulatory Operations Office on March 30, 1974 Written noti fication was made to Mr. James P. O'Reilly, Region I Regulatory Operations Office on April 1, 1974 In accordance with Section 6.7.2.A of the Technical Specifications, Appendix A of DPR-44 fer Uni t 2 De=ch 9ettem ate-ie D~.ar St=tien, the fe!!ening report is being submitted to the Directorate of Licensing as an Abnormal Occurrence.

Reference:

License Number DPR-44, Amendment No. 1 Technical Speci fication 3.6.D.2. (a)

Report No.: 50-277-74-17 Report Date: April 1,1974 Occurrence Date: March 29, 1974 Facility: Peach Bottom Atomic Power Station R.D. #1, Delta, Pennsylvania 17314 Identification of Occurrence:

Indication of bellows leak on reactor relief valve 71G.

Conditions Prior to Occurrence:

Plant at approximately 24% power during a start-up.

Description of Occurrence:

During a plant start-up with the reactor pressure stable at approximately 930 psig, the bellows leak indicator for rel'ef valve 71G illuminated. '

g 8402070465 740405 PDR ADOCK 05000277 V[' ,h 821$

m 4~ COPY SENT 7 a -

t REGION [" ,

Mr. A. Giambusso

• April 5,1974 Page 2 Designation of Apparent Cause of Occurrence:

Continued plant operation at signi ficant power levels has prevented investigation of this problem to date. Because the reactor power level was too high to permit a drywell entry at the time the bellows Icak indication was indicated, verification cf an actual bel-lows leak could not be accomplished. The overpressure relief valve  ;

function of this valve is assumed to be inoperabic.

Analysis of Occurrence:

The failure of the pressure relief valve function of one valve has no safety significance because sufficient relief valves are insts11ed to provide a 25 psig margin between peak pressure and the point at which the first safety valve opens with only 7 operable relief valves assuming a 3 second main steam line isolation and a neutron flux scram from full power. Ten relief valves are still operable.

Corrective Action:

Corrective action will be undertaken following the next shutdown. The Technical Specifications permit continued plant opera-cion for 30 days wi:r. one inoperanie sarety valve tunctior. ,t or.c relief valve. Fo11cwing shutdown, the leaking bellows indication will be verified and repairs initiated if required.

Failure Data:

Several bellows assemblies have leaked at the "0" ring joint in the past. Refer to A0 report 50-277-74-16 and A0 report 50-277, dated November 16, 1973.

Very truly yours,

/97kw3 M. J. Cooney f/

Asst. Gen 1'. Superinterident Generation Division cc: Mr. J. P. O'Reilly Director, Region I .

U.S. Atomic Energy Commission 631 Park Avenue King of Prussia, PA 19406 N