ML20118A707

Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,deleting Ref to App a of 10CFR55 in Spec 6.4.1 Re Operator Training & Qualification,Based on Issuance of NUREG-1021

ML20118A707
Person / Time
Site:	Byron, Braidwood
Issue date:	09/16/1992
From:	Simpkin T COMMONWEALTH EDISON CO.
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML20118A708	List: ML20118A707 ML20118A709
References
RTR-NUREG-1021 NUDOCS 9209250026
Download: ML20118A707 (4)

Text

- - - _ - -

..g2, ME

( :, -

[

I -

-C:mm nwrith Ediscn

~ 1400 opus Place

' Downers orove,'lltinois 60515 ~

September 16,.1992 Dr. Thornas E. Murley, Director:

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20556 Attn: Document Control Desk

Subject:

Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Application for Amendment to Facility O)erating License NPF-37, NPF-66, NPF-72 and NPF-77 N 3C_ Docket Nos 50145.4 A55 A56md_45Z.  :

Dear Dr. Me-ley:

Pursuant to 10 CFR 50.90, Commonwealth Edison CECO proposes to amend Apaendk A, Technical Specification of Facility Operati(ng Lice)nse NPF NPF-66, N PF-72 and NPF-77 The proposed amendment revises Section 6 to delete reference to superceded documents pertaining to the training of licensed operators.

A detailed description of the proposed change is presented in Attachment A.

The revised Technical Specification pages are contained in Attachment B.

The prgosed change has been reviewed and approved by both on-site and -

off site review n accordance with CECO procedures. CECO has reviewed this' proposed amendment in accordance with 10 CFR 50.92(c) and has determined that no significant hazards consideration exists. This evaluation is documented in Attachment C. An Environmental Assessment has been completed and is contained in Attachment .

D.

CECO is notifying the State of lilinois of our application for this amendment by.

transmitting a copy _of this letter and its attachments to the designated State Official.

4 2101G0 l

ZNLD/2145/1 *\' l Uf flgk 9209250026 920916 -

'PDR .ADOCK 0500o454 k W ? N)

//

.- ?f. .

I-

Dr. Thomas E. Murley Septcmbar 161992 To the best of my knowledge and belief the statements contained herein are true and correct. In some respects, these statements are not based on my personal knowledge but upon informatior aceived from other Commonwealth Edison and contractor employees. Such it.k. mation has been reviewed in accordance with Company practice and I believe it to be reliable.

Please direct any questions regarding this matter to this office.

Sincerely,-

&w')O.

T.W. Simpkin Nuclear Licensing Administrator cc: R.M. Pulsifer, Project Manager - NRR J.B. Hickman, Project Manger - NRR S.G. DuPont, Resident inspector - Braidwood W.J. Kropp, Resident inspector - Byron Document Control Desk - NRR Region lli Office Office of Nuclear Facility Safety - IDNS q Q 'o fL m.b c e t er. d 8t -

{7:::

l = = AL OFFICI  :~ ~SEAL'~-

Ol' 4j 4 - 9 g ( ll MARYELLEN D. LONG NOTARY PUBliC STATE OF ILUNDIS vu,v/ 0/ uMfGl' MY COMMISSION udRES 8/1V93

_ =====_

l ZNLD/2145/2 l'

ATTACHMENEA DETAILED DESCRIPTION OF_THE PROPOSED CHANGES Doccription of the Curront Operating Licenso (OL) Roquiroments:

Specification 6.3.1 imposes additional requirements for the qualification of licensed Operators and Senior Operators. These requiroms are delineated in Section A of Enclosure 1 of the MatcA 28,1980 Nuclear Regulator / Commission (NRC) letter to all licens90s. Theso requiroments are in addition to those mandated by Title 10, Code o Federal Regulations, Part 55 (10 CFR 55).

Specification 6.4.1 states that the requalification training program of licensed Operators and Senior Operators will comply with the requirements of Appendix A of 10 CFR 55.

Specification 6.4.1 also imposes udditional recuirements for the requalification traini'.g of u~;.nsed Operators and Senior Operators. These requirements are delineated in Section C of Enclosure 1 of the March 28,1980 NRC lottor to alllicensees. These requirements are in addition to those mandated by 10 CFR 55.

Bason 50 Cunont OL Roquirerr.9nts:

The requirements of those Specifications are based on the provisions of NUREG 0452, Standard Technical Speci' alons for Westinghouse Pressurized Water Reactors,in effect at the time that Byrv , and Braldwood Stations were licensed.

Description of the Ned for Amending the Technical Specifications:

The requirements of the March 28,1980 NRC letter to all licensees were superceded by the issuance of NI' REG-1021, Operator Licensing Examinor Standards.

Additionally, the reference to Appendix A of 10 CFR 55 is no longer correct. Anendix A was incorporated into the body of the regulation during a previous revision o' She regulation.

ZNLD/2145/3

t t

^

l DesJption of the Proposod Amendm.mt:

The proposed amendment would delete the reference to the March 28,1980 NRC 't letter to all licensees in Specifications 6.3.1 and 6.4.1.

The roposed amendment would o!so # fate the reference to Appendix A of j 10 CFR0p5 in specification (1,4.1.

Brasis for the Proposed Amendment: r The purpose of the March 28,1980 NRC letter to alllicenseea was to set forth revised criteria to be used by the NRC staff in evaluating reactor operator training and licensing under the regulations in effect at the time of the letter. These ravlsed criteria J were established based on the Commission review of the Three Mlle Island Unit 2 i accident which occurred on March 28,1979. The letter stated that the Commission review in the area of operator training and qualification would continue and could be expected to result in additional criteria being established. The letter also stated that final requirements would be est ; allshed through rule making proceedings.

The continued Commission review in the area of operaton training and qualification >

resulted in revisions to 10 CFR 55 and the issuance of NUREG-1021, erator Licensing Examiner Standards, which provides guidance regarding the i plementation  :

of 10 CFR 55 requirements. These requirements supercede those delineated in the March 28,1980 NRC letter to all licensees.

- Since the initial license examinations at both Byron and Braldwood Stations, -

oprator training and qualification has been evaluated against the requirements of N UREG 1021.  ;

The reference to Appendix A of 10 CFR 55 is no longer correct since the requirements of what used to be Appendix A have been incorporated into the oody of the regulation. Furthermore, it is unnecessary to commit to compliance with

requirements already mandated by regulation, P

Schedular Requirements: ,

L There are no schedular restraints associated with this proposed amendment.

l l

p ZNLDt2145/4 ,

n a- _- - . _ _ . - __ _ . - ._. __ _