05000369/LER-1981-101, Forwards LER 81-101/03L-0.Detailed Event Analysis Encl

Forwards LER 81-101/03L-0.Detailed Event Analysis Encl

ML20009E709
Person / Time
Site:	McGuire
Issue date:	07/16/1981
From:	Parker W DUKE POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20009E710	List: 05000369/LER-1981-101, Forwards LER 81-101/03L-0.Detailed Event Analysis Encl 05000369/LER-1981-101-03, /03L-0:on 810617,10 Batch Releases of Used Powdex Resin Were Transferred to Chemical Treatment Ponds W/O Making Estimates of Sr-89 & Sr-90 Per Previous Monthly Analysis.Caused by Health Physics Group Error.Mod Requested
References
NUDOCS 8107280380
Download: ML20009E709 (3)

LER-1981-101, Forwards LER 81-101/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
3691981101R00 - NRC Website

text

r o

~

OFFICI AL COPY DUKE POWER COMPANY Poven Beti.nixo 422 SouTn Cucacu Srazer, Ciunt.orTE, N. C: 2s242

'I.'

..,4 v, - As A M O. PA R K E R J R.

WCP Persiormt TEttraoset AntA 704 srca-Pacoucno~

July 16, 1981 v3-does Mr. James P. O'Reilly, Director

,g,

[/)

U. S. Nuclear Regulatory Commission s v

'kf N

'{

Region II

(, ' h y y

[,,,,

101 Marietta Street, Suite 3100 Atlanta, Georgia 30303

[ JUL 2 8 BSM -8 Re: McGuire Nuclear Station Unit 1

(

,,3, qCgd Docket No. 50-369 p

p

Dear Mr. O'Reilly:

g Please find attached Repottable Occurrence Report R0-369/81-101. This report concerns Technical Specification 4.11.1.5; "The quantity of radioactive material contained in each ba ch of slurry (used powdex resin) to be transferred to the chemical treatment ponds shall be determined to be within the above limit by analyzing a representative sample of this slurry." This incident was considered to be of no significance with respect to the health and safety of the public.

Ver truly yours,

/

d m _ -

William O. Parker, Jr.

PBN/pw Attachment cc:

Director Mr. Bill Lavallee Office of Management & Program Analysis Nuclear Safety Analysis Center l

U.S. Nuclear Regulatory Commission Post Office Box 10412

. Washington, D. C.

20555 Palo Alto, CA 94303 Ms. M. J. Graham Resident Inspector - NRC McGuire Nuclear Station hl l hM05000369 80 810716 D

S PDR v

r McGUIRE NUCLEAR STATION REPORTABLE OCCURRENCE Report Number:

81-101 Report Date:

July 16, 1981 Occurrence Date: June 17, 1981 Facility: McGuire Unit 1, Cornelius, N. C.

Identification.of occurrence:

Esticates of Sr-89 and Sr-90 batch concentrations (based on previous monthly composite analysis) were not performed on used powdex resin which was transferred to on-site Chemical Treatment Ponds.

Conditions Prior to Occurrence: Mode 5, Cold Shutdown, prior to initial criti-cality.

Description of Occurrence:

Estimates of Sr-89 and Sr-90 based on previous monthly analysis of batch releases of used powdex resin to on-site Chemical Treatment Ponds were not made.

This was reportable pursuant to Technical Speci-fication Surveillance requirement 4.11.1.5.

Analysis of Occurrence:

Ten batch releases (%5,000 gal /ea) of slurry (used powder resin) had been transferred to the Chemical Treatment Ponds (CTP) prior to identification of this incident.

Each of these releases was sampled and analyzed for radioactivity; the identification and concentrations of specific isotopes, such as I-131, I-133, and principal gamma emitters, were determined.

It was felt that this analycis was required for the plant in its current state of operation.

Analyzation of a sample for~Sr-89 and Sr-90 requires complex and lengthy pro-cedures.

The Station does not have the capability of analyzing a sample for Sr isotopes; therefore, samples must be shipped off-site to a private vendor for analysis.

Tla turn around time to receive the sample results from the vendor is 3-6 weeks.

A member of the resident NRC staff ras questioned concerning this sampling re-quirement and other obscurities within 4.11.1.5.

It was determined that the station was in error with the current Technical Specification but that Technical Specification requireaent 4.11.1.5 is incorrect and, if literally interpeted, would unreasonably restrict station operation.

For example: The results of resin'sent to the vendor in April, may not be returned until June. Thus, no releases could be made for the month of May.

As a result, no releases could be made in June or in subsequent months.

Upon discovery of the discrepancy, samples of resin were shipped to the con-tracted, off-site vendor for analysis.

Additionally, steps were taken to have the NRC re-evaluate the requirements of 4.11.1.5 and consider modifying it to incorporate a. workable solution with which the station could better meet this surveillance requirement.

Report Number 81-101 Page 2 Apparent Cause: The requirement for the analysis of powdex resin for Sr-89 and Sr-90 is obscurely located in the definition of a component of an equation which is found in Surveillance Requirement 4.11.1.5.

The Health Physics _ group had incorrectly assumed that this requirement was not applicable until after the reactor had gone critical and/or a primary to se ondary leak had occurred.

Corrective Action

This deficiency was brought to the attention of an NRC in-spector who ccnfirmed that the incident was a reportable occurrence.

Samples of resin were sent to an off-site vendor for Sr-89 and Sr-90 analysis.

Additionally, Duke Power will apply to the NRC for a change or an official interpretation of the affected surveillance requirement.

Safety Analysis

Sr-89 and Sr-90 are bone-seeking isotopes which could have an affect on one's body burden if injected orally.

Their detection in samples is difficult to obtain because their presence is obscurred by other beta-emitting isotopes.

Laboratory analyses have confirmed that no activity greater than normal background has been present in any of the batch releases of powdex resin to the CTP's.

The results of the most recent sample of powdex resin (June 11, 1981) which was analyzed by an off-site vendor substantiated this.

Thus, neither the health and safety of the public cr the environment were affected by this incident.

v-

--.m

,,y r-.