ML20155B241

Application for Amend to License DPR-16,allowing Removal of High Pressure Scram Function When Reactor Head Removed or Unbolted

ML20155B241
Person / Time
Site:	Oyster Creek
Issue date:	09/28/1988
From:	Fitzpatrick E GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20155B229	List: ML20155B224 ML20155B241 ML20155B245
References
NUDOCS 8810060245
Download: ML20155B241 (4)

Text

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4 0YSTER CREEK NUCLEAR GENERATING STATION l

PROVISIONAL OPERATING  !

LICENSE NO. DPR-16 l

i l

TECHNICAL 3PECIFICATION 1 CHANGE REQUEST NO.174 I DOCKET NO. 50-219 ,

t

! Applicant submits by tilis Technien1 Specification Ch6nge Request No.174 to ,

1- tue 0.yster Cred Nuclear Generating Station Technical Specifica', tons, modified

pagos 3.i-8, and 3.1-19.  ;

/

By: /

E. E. Fitzpatrick

~

i, Vice President and Of rector }

Oyster Creek  ;

j It i Sworn to and Subscribed before me this 28th day of September, c/ 1988.

vn d

[ A Notary y ic o M ew Jer'.sey

/ CAROL A. SCARPlNATO NOTARY PUBLIC 0F NEW JERSEY

My Commission E:pires Feb.27,1991 i G010060245 000920 PDR ADOCK 05000219 P PNu

0YSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL LICENSE DPR-16 DOCKET NO 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 174 The Applicant hereby requests the Commission to change Appendix A of the above captioned license as follows:

1. Section to be Changed:

Table 3.1.1.A.2, and notes

2. _ Extent of Change:

a. Table 3.1.1.A.2: add note "11" to the Start Up mode,

b. Add note "kk" to the Table 3.1.1 notes.

c. Add note "11" to the Table 3.1.1 notes.

3. Change Requested:

Replace old pages 3.1-8, and 3.1-19 with new pages 3.1-8, and 3.1-19,

4. D,iscussion Refer to No Significant Hazard Analysis which immediately follows.

0YSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL LICENSE DPR-16 DOCKET NO. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 174 This Technical Specification Change Request has been determined to contain No Significant Hazards as required by 10CFR50.91. These evaluations are spect fled in 10CFR50.92.

The requested change adds a reference to no'te "11" in the startup mode for the High Reactor Pressure Scram function. Proposed note "11" will state:

"This function not required to be operable with the reactor vessel head recoved or unbolted."

Table 3.1.1 note "kk" is being reserved for another Technical Specification change request presently under review.

When reactor temperature is less than 212*F and either the vessel-head is removed or unbolted, there is no possibility of a major reactor pressure excursion. As an excursion is not possible, the instrumentation required to scram the reactor in response to an excursion serves no purpose.

Additionally, the Boiling Water Reactor Standard Technical Specifications specifically state that the High Pressure Scram function is not required when the head is unbolted or removed in the STARTUP mode. This request more closely aligns the Oyster Creek Nuclear Generating Stetton Technical Specifications with the Beiling Water Reactor Standard Technical Specifications.

Therefore the requested change has been determined to contain No Significant Hazards in that it does not:

1. Involve a significant increase in the probability or consequences uf an accident previously evaluated.

The requested change is applicable only under those previously evaluated conditions where the function has been determined to be not required. Therefore, it does not increase the probability or consequences of any previously evaluated accident.

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2. Create the possibility of a new or different kind of accident from any accident previously evaluated.

As the requested change is only applicable to those conditions where the protective function has been determined to be not required, no new or different kind of accident is created, s

3. Involve a significant reduction in the margin of safety.

As the applicability of the requested change has been limited to those times when the function is not required, no reduction in a margin of safety is possible.