ML20139A311

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Corrected Ltr Forwarding Rev to Effluent & Waste Disposal Rept,Liquid Effluents - Summation of All Releases,Jan-June 1985. Values for Average Diluted Concentration During Period Corrected
ML20139A311
Person / Time
Site: Limerick 
Issue date: 11/13/1985
From: Alden W
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To: Murley T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20138A008 List:
References
NUDOCS 8512110501
Download: ML20139A311 (3)


Text

D 4

PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 (2151841-4000 November 13, 1985 Docket No. 50-352 l

Dr.: Thomas E. Murley, Administrator Region I.

U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

SUBJECT:

Revision to Semi-Annual Ef fluent Releases Report No. 2 January 1, 1985 through June 30, 1985 Limerick Generating Station

Dear Dr. Murley:

Enclosed is a revised " Liquid Ef fluent-Summation of all Releases" page to the Semi-Annual Ef fluent Releases Report. 2 for Limerick Generating Station. Unit 1.

The Semi-Annual Effluent ReleasesLReport was submitted on August 29, 1985 in compliance

- with the Annual Reporting requirements of Technical Specification 6.9.1.8 of Operating License NPF-27 in accordance with Regulatory Guide l.21 and Regulatory Guide 10.1.

A revised page is being submitteds to correct errors, due t'o an aiministrative oversight, in the. values for the " Average Diluted Concentration During Period" line for the first and.

second quarters of 1985 ' as presented under-Sections A.2 and B.2.

-Limerick Generating Station uses an in-house computer.

system to correlate and compute certain of the data submitted in the Semi-Annual Ef fluent Release Reports.

At the time of the original submittal of the Semi-Annual Ef fluent Release Report _ No.

2: for Limerick, the computer program capability was limited to exponents to the base ten (10) of less than or equal to nine

.(09), i.e. E+00 through E+09.

For the original submittal, the computer expressed the data under Section F of this page with

= exponents of E+01 when the actual exponents should have been

~

'E+11.

(Example:

the data for Section F for first and second

. quarters as expressed by the computer were 0.523E+01 and 0.141E+01 respectively rather than 0.523E+11 and 0.141E+11 respectively).

This progam limitation was recognizied and the exponents for the data under Section F were changed to E+11 by hand before the Semi-Annual Ef fluent Release Report No. 2 was submitted.

8512110501 851122 PDR. ADOCK 05000352 R

PDR

L t

November 13, 1985 Page 2 I'

Subsequent to the submittal of Report No. 2, it was

- realized that the computer utilizied its values in Section F to compute the values in Sections A.2 and B.2 (i.e. A.1/F = A.2 and B.1/F = B.2) and had used an exponent of E+01 instead of E+11 in order.to compute the. values for Sections A.2 and B.2.

The values in Sections A.2 and B.2 have been changed on this revised page to provide _ the proper data.

To preclude a future occurrence, the program for the in-house computer has been changed to accept values with exponents up to E+99.

The corrected data is indicated by a vertical bar in the margin of the revised page.

If you have any questions, please do not hesitate to contact us.

Very truly yours, W. M. Alden l.

Engineer-In-Charge Licensing Section Attachments Ecc Document Control Desk U.S.

Nuclear Regulatory Commission Washington, D.C.

20555 E. M. Kelly, Senior Site Inspector l

See Service List l

l

cc Troy B. Conner, Jr., Esq.

Ann P. Hodgdon, Esq.

Mr. Frank R. Romano Mr. Robert L.. Anthony Ms. Phyllis Zitzer i

Charles W. Elliott, Esq.

Zori G. Ferkin, Esq.

Mr. Thomas Gerusky 4

Director, Penna. Emergency Management Agency Angus Love, Esq.

2 David Warsan, Esq.

5 Robert J. Sugarman, Esq.

Kathryn S. Lewis, Esq.

Spence W. Perry, Esq.

Jay M. Gutierrez, Esq.

Atomic Safety & Licensing Appeal Board Atomic Safety & Licensing Board Panel Docket & Service Section (3 Copies)

E. M.

Kelly Timothy R. S.

Campbell September, 1985 i

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