ML20236T475

TS Change Request 257 to License DPR-16,making Several Changes to Section 6 of Tech Specs & Make Other Changes of Administrative Nature

ML20236T475
Person / Time
Site:	Oyster Creek
Issue date:	07/21/1998
From:	Roche M GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20236T463	List: ML20236T461 ML20236T475 ML20236T481
References
NUDOCS 9807280206
Download: ML20236T475 (4)

Text

_ - _ _ _ _ _ _ _ _ _ _ _ __

i*

OYSTER CREEK NUCLEAR GENERATING STATION f

l OPERATING LICENSE i

NO. DPR-16 l

TECHNICAL SPECIFICATION CHANGE REQUEST NO. 257 DOCKET NO. 50-219 l

Applicant submits by this Technical Specification Change Request No. 257 to the Oyster Creek Nuclear Generating Station Technical Specifications, modified pages 2.3-7,3.3-5,3.3-8a,3.7-4, 3.8-2, 6-1,- 6-2, 6-2a, 6-3, 6-5, 6-6, 6-8 and 6-9.

By: 4 Michael B.' Roche Vice President and Director ,

Oyster Creek Sworn to and Subscribed before me this 8/ 40 day of .1998.

A LasIn. M s A Notary Public ofNew Jersey OtAMA M. De8UMNO '

NOTARY PLECOF mp m m /3 atw 9807280206 980721 PDR ADOCK 05000219 P PDR o-.____________

[.

I I. . TECHNICAL SPECIFICATION CHANGE REQUEST (TSCR) NO. 257 GPU Nuclear, Inc. requests that the following replacement pages be inserted into the existing Technical Specifications:

l . Rsplace existing pages 2.3-7,3.3-5,3.3-8a,3.7-4,3.8-2,6-1,6-2,6-2a,6-3,6-5,6-6,6-8 i

and 6-9 with the attached revised replacement pages 2.3-7, 3.3-5,3.3-8a,3.7-4,3.8-2, 6-1,6-2,6-2a,6-3,6-5,6-6,6-8 and 6-9.

II. REASON FOR CHANGE This TSCR modifies a number ofitems in the " Administrative Controls" section of the l Technical Specifications. Specification 6.2.2.2 (a), which details the minimum duty shin staffing, has been modified to provide some operational flexibility to accommodate -

l unexpected absence of on-duty shift crew members. Specification 6.2.2.2 (j) refers to the l Manager, Plant Operations and that position was previously eliminated. In several places the term "Vice President" has been replaced with the term " Corporate Officer". While l

the latter term includes the Vice Presidents, it also includes the President, GPU Nuclear.

L The maximum time in which to forward audit reports to the responsible management i po'sitions has been reduced from 60 days to 30 days. The inclusion of these changes has led to changes in pagination.' Finally, several typographical errors have been corrected.

Also included are three unrelated changes to the Bases of Specifications 2.3,3.3, and 3.8.

These changes have been reviewed in accordance with 10 CFR 50.59 and determined to

, . contain no unreviewed safety questions. The change to the Basis of Specification 2.3 clarifies the applicability of the definition of top of active fuel (TAF). The change to the Basis of Specification 3.3 updates and clarifies the analyzed number of thermal cycles l _

(i.e., heatup / cooldown) used to confirm that the original allowable fatigue usage limit is maintained. The change to the Basis of Specification 3.8 makes the Basis statement b consistent with a change to the Specification approved by an earlier Amendment.

III. SAFETY EVALUATION JUSTIFYING CHANGE The provision which provides operational flexibility in meeting the minimum on shin crew staffing is only applicable in certain circumstances and for a limited period of time j (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />). The provision parallels one in the Three Mile Island Technical Specifications and is consistent with the Standard Technical Specifications. A decrease in staff for a short time on limited occasions is not safety significant. In addition,10 CFR 50.54 (m), i which establishes the minimum staffing by operators and senior operators, permits l temporary deviations from the minimum in accordance with criteria in the Technical  :

Specifications.'

l I

I

l

, The position Manager, Plant Operations was eliminated and the duties and I responsibilities were assumed by the Plant Operations Director. The person in that

. position has maintained an SRO license. I In defining the lines of authority and responsibility, the Oyster Creek Technical Specifications currently use the term Vice President to indicate the senior management person in an organizational unit. The use of that term, however, was not intended to exclude the President, GPU Nuclear. Until recently, the individuals who report to the President, GPU Nuclear did not include personnel responsible for any aspect of the Safety Review Process. A recent reorganization, however, placed the Nuclear Safety Assessment organization as a direct report to the President, GPU Nuclear. This change clarifies that the President, GPU Nuclear has the same responsibilities relative to the Safety Review Process as the Vice Presidents.

The maximum period between the completion of an audit and the forwarding of the audit report for action to the responsible management positions has been changed to 30 days.

l This change is more restrictive than the current limit of 60 days and is consistent with  !

Regulatory Guide 1.144 and the associated ANSI Standard.

The inclusion of the additional provisions in Specification 6.2.2.2 has resulted in the i repagination of the two subsequent pages. In addition, several typographical errors have been corrected. Specifically, the word " retaining" has been corrected to the proper word i

" retraining", an inaccurate reference to the Code of Federal Regulations has been rectified and a letter date in a reference to Specification 3.7 has been corrected.

.IV. NO SIGNIFICANT HAZARDS CONSIDERATION GPU Nuclear has determined that this TSCR poses no significant hazard as defined by 10 CFR 50.92.

1. State the basis for the determination that the proposed activity will or will not increase the probability of occurrence or consequences of an accident.

The activity does not alter the design, function or manner of operation of any structures, systems or components. Therefore, this activity does not increase the probability or consequences of an accident l

2. State the basis for the determination that the activity does or does not create the possibility of an accident or malfunction of a different type than any previously

' identified in the SAR.

The activity does not alter the design, function or manner of operation of any structures, systems or components. Therefore, this activity does not create the l

p .

I*

)

• l possibility of an accident or malfunction of a different type than any previously l ,

identified in the SAR.

k

3. State the basis for the determination that the margin of safety is not reduced.

The activity does not alter the design, function or manner of operation of any i structures, systems or components. In addition, a decrease in staff for a short period of time on limited occasions is not safety significant and permitted by 10 CFR 50.54 (m). Therefore, this activity will not reduce the margin safety. j l

V. IMPLEMENTATION GPU Nuclear requests that the amendment authorizing this change be effective upon issuance.

I l

i I

- _ _ _ _ _ _ - _ - - _ - - - _ _ _ - .