ML19261F313

RO 77-22/1T:on 770825,B&W-required Operating Restrictions on Decay Heat Removal Pumps Found Contrary to Description of Pump Operating Capability Per Fsar.Caused by B&W Failure to Perform Safety Evaluation.Corrective Action by 770923.W/LER

ML19261F313
Person / Time
Site:	Crane
Issue date:	09/09/1977
From:	Herbein J METROPOLITAN EDISON CO.
To:
Shared Package
ML19261F314	List: 05000289/LER-1977-022-01, /01T:on 770825,during Normal Operation Restrictions Placed on Decay Heat Removal Pumps Found Contrary to Pump Operating Capability Per Fsar.Restrictions Placed on Pump by B&W Due to Pump Failure at Other Util ML19261F313
References
GQL-1228, NUDOCS 7910250774
Download: ML19261F313 (4)

Text

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..NRC DISTRIBUTION PoR PART 50 DOCKET MATERIAL INCIDENT DEPORT oATE cr occuuENT FROM: Metropolitan Edison Co iTO:

9 9-77 B H Grier Reading, Pa l

J G Herbein

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i CEsCRIPTION EN CLCSU R E l-Licensne Event Recort (RC# 77 22/lT) on 8 25-7:

concerning operating restrictions en the decay heat removal pumps found contrary to pumps ep r-ating capacity as defined in tech soacs......

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? TANT NAME: Three Mile Island #1 l

9-15 77 ehf NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J. COLLINS

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• POM PMQ0A133 METROPOLITAN EDISON COMPANY _ _

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POST OFFICE BOX $42 READING, PENNSYLV ANI A 19603 TELEPHONE 215 - 9290001 September 9, 1977 GQL 1228 Mr. Boyce H. Grier, Director Office of Inspection and Enforcement, Regicn I ddI,' -

I U.S. Nuclear Regulatory Cct=ission

-3; 631 Park Avenue

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King of P*ur sia, PA 19hC6 s

Dear 35.r

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Decket No. 50-289 Operating License No. DPR-50 In accordance vith the Technical Specifications of our Three Mile Island Nuclear Station, Unit I (TMI-1), we are reporting the following reportable occurrence:

1)

Report Ncnber:

77-22/lT 2a) Required Report Date: 9/8/77*

2b) Date of Cccurrence: 8/25/77 3)

Facility:

fhree Mile Island Nuclear Station, Unit 1 h)

Identification of Occurrence:

Title:

Restrictions were Placed on the Decay Heat Receval Pumps Type:

A reportable occurrence as defined by 6.9 2. A.9 'n that required operating restrictions on tne Decay Heat Re= oval Pumps were found centrary to the description of the pumps operating capability in the FSAR.

5)

Conditions Prior to Occurrence:

Power:

Core 1005 Elec.

811 MWe Gross RC Flow:

lh5x106 lb/hr RC Pressure:

2163 psig

}k02

{

RC Temp:

579CF PRZR Level 227 inches PR' 'S Te- -

652c

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gQ{jgO3hO

• A detailed report regarding Met-Ed's additional September 3/h vibraticn test, UT tests, and stress analysis to confirm the continued reliability of TMI-l Decay Heat ?u=ps was presented to R. W. Reid at the NRR 3ethesda offices on 9-8-77.

Mr. Boyce H. Grier, Director September 9, 1977 GQL 1228 6)

Descriptien of Occurrence:

During the preparatien of a procedural change to incorporate recent recc==endations by the Nuclear Steam Supply Systems (NSSS) vender restricting the operations of Decay Heat Removal Pumps at mini =u= recirculatien flow rates, it was recognized that these restrictions were contrary to the FSAR statement that the Decay Heat Removal Pu=ps could operate " indefinitely" in the minimum recirculation mode (FSAR Secticn 6.1.2.1.2).

These restrictions were developed to minimize the potential for an occurrence similar to a Eecay Heat Removal Pu=p shaft failure which had been reported at ancther utility's site.

7)

Apparent Cause of Cecurrence:

The Decay Heat Remova.1 Pu=p shaft at another utility's site failed during preoperational testing.

Therefore, operating restricticns were prc=ulgated by the NSSS vendor without a full investigation into the cause for failure and without a formal safety analysis by the NSSS vender.

3)

Analysis of Occurrence:

The analysis of the reliability of the Decay Heat Removal Pu=ps has been detailed to the US:TEC Director of Nuclear Reactor Begulation by a separate letter dated 9/6/77. The conclusien of that analysis was that although lov flow rates can lead to relatively higher leads on the pu=p, vendor experience with similar pumps indicates that intermittent operaticn at recirculation flow rates, totalling many hours over the life of the pu=ps, vill not damage the pumps; furthermore, the requirements of the safety analysis (FSAR Section ik) for operaticn of the Decay Heat Removal Pu=ps in the recirculation mode can be met by the presently designed syste= and equipment.

9)

Corrective Action:

(To be submitted on September 23, 1977, per telecen with Mr. Struter en September 9, 1977.)

e

Mr. foyce H. Grier, Director September 9, 1977 GQL 1223

10) Failure Data:

Decay Heat Removal Pump Manufacturer: Worthingten Model "o.:

3 Wn ISL Part No.

2 (shaft)

Material:

SA-56h Type 630 ET 1150 Similar Occurrence:

Ncne c'ncerely,

'/

J. G. Herbein Vice President JGH:DGM:ies

Attachment:

LER 1482 032

.