ML19323D433

Forwards LER 80-009/01T-0

ML19323D433
Person / Time
Site:	Peach Bottom
Issue date:	05/16/1980
From:	Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19323D434	List: ML19323D433 ML19323D445
References
NUDOCS 8005210557
Download: ML19323D433 (2)

Text

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ms PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHI A, PA.19101 (2:51 e41-4000 2

} r,ay 16, 1930 t

t ir. Boyce M. Grier, Director j Office of Inspection & Enforcenent R e p,l o n I United States Muclear Regulatory Counission 631 Park Avenue K i n g, of Prunsia, PA 19406

SUBJECT:

Licens,e Event Report Narrative D e_s c r i_ p t i o n

^~ The following occurrence was reported to I: r . Bettenhousen, US !!u c l e a r Regulatory Counission. Region I, Office of Inspection and Enforcement on Itay 2, 1930.

l l

Reference:

Docket Nos. 50-277 & 50-278 Report No.: LER 2-80-9/lT Report Date: It a y 16. 1900 Occurrence Date: Ziny 2, 1980

Facility: Peach Bottom Atomic Power Station

, , RD 1 Delta, PA 17314 i

T e c h n i c a l, S,p e c i f_i c a t i o n Reference _ '

l Technical Specification 3.7.C.1 states in part that

" Secondary containment i n t e r; r i t y shall be maintained during all

.n o d e s of plant operation except when all of the following conditions are act." Part (d) states " T ..e fuel cask or irradiated fuel is not being moved in the reactor building."

Descr1 11 tion of the Event, l

On llay 2, 1930, an irradiated fuel bundle was moved in the spent fuel pool.for.a lead test assembly inspection. A secondary

. containment leak test performed on the. sane day indicated that

! the~ containment boundary passed flow in excess of the limit in Tech. Spec. 4.7.C.I.a. .This test was performed to verify-that J

scossio J 5 7

ss l

Mr. Boyce H. Grier Page 2 4

I secondary containment had been re established following the removal and replacement of an RHR pump room hatch on May 1, 1980.

An investigation revealed that the cause of the secondary containment leak rate test failure was the renoval of steam and feedwater line reactor building penetration boots on May 1, 1980.

These boots were removed so they could be replaced with an improved naterial nore suited to the tenperature and radiation environment that exists at full power.

Cause of Event The cause of this event was the lack of a procedure which adequately specified the conditions under which the penetration boots could be renoved. In addition, the procedure for removal of an RHR notor via its respective hatch did not properly address secondary containment considerations.

C o n s e q u e n_c_e_s of E,v e n_t Full secondary containment capability was not maintained during the tiae that the one fuel bundle was renoved, however. no probleus were encountered during novenent of this bundle which would have released fission products. Probable consequences of this event are rai nina l .

Corrective Actio_n All fuel movement within the reactor building was suspended on May 2, 1980, and an administrative block was placed on the refueling bridge to ensure that no fuel movement would occur while the penetration baots were replaced. A procedure for replacement of the penetration boots was generated which requires notification of and specific permission from shift supervision

,before renoval of the penetration boots. The penetration boots we,re subsequently replaced and secondary containment integrity was verified by perfornance of the appropriate surveillance test on May 9, 1980.

Locking nochanisms are to be installed on secondary containment equipment hatches to ensure that shift supervision is aware of and can terninate plans to lift these hatches if

, secondary containnent is required. In addition, the procedure for renoval of an RIIR actor will be revised to address secondary containment considerations.

l. Very truly yours,

4. 1 r

%l1lvlt)/

1 i w j '.,j. Cooney[

M j S u gie ri n t e n d e h t f Generation Division - Nuclear cc: Director, NRC - Office of Inspection and Enforcenent Mr. Norman Haller, NRC - Office of Management & Program Analysis

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