ML20153F789

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Ack Receipt of 880808 Response to NRC Re Actions Taken to Correct Violations Noted in Insp 50-333/88-07
ML20153F789
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 08/30/1988
From: Bellamy R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Radford Converse
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
References
NUDOCS 8809070475
Download: ML20153F789 (2)


See also: IR 05000333/1988007

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AUG 3 01933

Docket No. 50-333

Power Authority of the State of New York

James A. FitzPatrick Nuclear Power Plant

ATTN: Mr. Radford J. Converse

Resident Manager

P. O. Box 41

Lycoming, New York 13093

Gentlemen:

Subject: Inspection No. 50-333/88-07

This refers to your letter dated August 8, 1988, in response to our letter

dated July 7, 1988.

Thank you for informing us of the corrective and preventive actions documented

in your letter. These actions will be examined during a future inspection of

your licensed program.

Your cooperation with us is appreciated.

Sincerely.

Ovina! Sign:d IM

Rudd R. Ocuam/

Ronald R. Bellamy, Chief

Facility Radiological Safety

and Safeguards Branch

Division of Radiation Safety

and Safeguards

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J. Phillip Bayne, President

Mr. John C. Brons, Executive Vice President

A. Klausmann, Senior Vice President - Appraisal and Compliance Services

R. L. Patch, Quality Assurance Superintendent

George M. W11verding, Manager Nuclear Safety Evaluation

Gerald C. Goldstein, Assistant General Counsel

R. E. Beedle Vice President Nuclear Support

S. S. Zulla, Vice President Nuclear Engineering

R. Burns, Vice President Nuclear Operation

Dept. of Public Service, State of New York

State of New York, Department of Law

Licensing Project Manager, NRR

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August 8, 1988

JAFP-88-0744

U.S. Nuclear Regulatory Commission

Attention: Docu.nent Control Desk

Mail Stop Pl-137

Washington, D.C. 20555

SUBJECT: JAMES A. FITZPATRICK NUCLEAR POWER PLANT

DOCKET No. 50-333

EMERGENCY RESPONSE FACILITIES INSPECTION NO. 88-07

RESPONSE TO OPEN ITEMS

REFERENCE: 1. NRC letter, R. R. Bellamy to R. J. Converse

dated July 7, 1988 regarding NRC Inspection

50-333/88-07, Emergency Response Facilities

Dear Sir:

The NRC transmitted inspection Report No. 50-333/88-07 as an

attachment to Reference 1. This inspection repo t summa-

rized the results of an NRC inspection of the FitzPatrick

Emergency Response Facilities (ERF) during the week of May

16-20, 1988.

The report identified three open items. This letter de-

scribes the Authority's corrective action along with an

implementation schedule for each.

The three open items identified are restated below:

1. Dose calculation procedures do not contain a method for

calculating offsite doses resulting from a real tiee

accident in which the source term is leakage through

the drywell boundary and whether any other credible,

unmonitored accident release pathways exist for which

similar methods should be developed (50-333/88-05-01).

2. The validation and verification documentation for the

Class A Dose Assessment Model is incomplete (50-333/

88-05-02),

3. There is no formalized method for controlling and

documenting the maintenance of the dose assessment

model (i.e. MMRAS and IDAC) (50-333/88-05-03).

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TO: U.S.N.R.C. August 8, 1988

FROM: R. CONVERSE JAFP-88-0744

SUBJECT: INSPECTION NO. 88-07 Page 2

Response to Open Items (Corrective Act. ion and Schedule)

1. A 31 ant procedure will be developed for determining

raciological source terms for use in dose calculations

based on drywell radta. tion monitor readings and the

maximum allowabic containment leak rate as specified in

the FitzPatrick Technical Specifications. This proce-

dure will also include steps to identify credible,

unmonitored accident release pathways.

This procedure will be implemented by January, 1989.

2. A Validation and Verification program will be developed

for th computer programs that are part of the Fitz-

Patrick Meteorological Monitorin and Radiological Dose

Assessment Sy s t em - (MMRAS ) . A methodology similar to

that used to validate the FitzPatrick Offsite Dose

Calculation Manual (ODCM) will be used. The validation

and verification methodology will be documented in a

program report. The program will also develop and

document a detailed test pisn.

This program will be complete by May, 1989.

3. A plant procedure for the control and maintenance of

computer software is currently under development. This

procedure will be implemented to conttol revisions to

aoth MMRAS and IDAC (Interim Dose Assessment System)

computer programs.

This procedure will be iniplemented for MMRAS and IDAC

by May, 1989.

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CC: H. Abelson (U.S.N.R.C.)

W. Russell (U.S.N.R C. Region I)

A. Luptak (U.S.N.R.C. Resident Inspector)

W. Ferner.dez

D. Lindsey

E. Mulcahty

V. Wal:

M. Prarie

D. Ackley

G. Re (WPO)

J. Kelly (kTO)

J. Gray (WP0)

C. Faison 650)

WPO Recor.h inter

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