ML20205P848

TS Change Request 267 to License DPR-16,modifying Number of Items in Sections 2 & 3 of Ts,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4

ML20205P848
Person / Time
Site:	Oyster Creek
Issue date:	04/15/1999
From:	Roche M GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20205P845	List: ML20205P841 ML20205P848 ML20205P853
References
NUDOCS 9904210004
Download: ML20205P848 (7)

Text

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i OYSTER CREEK NUCLEAR GENERATING STATION i

OPERATING LICENSE NO. DPR-16 4 i

TECHNICAL SPECIFICATION CHANGE REQUEST NO. 267 DOCKET NO. 50-219 Applicant submits by this Technical Specification Change Request No. 267 to the Oyster Creek Nuclear Generating Station Technical Specifications, modified pages 1.0-3, 1.0-4, 2.3-3, 2.3-4, 2.3-5, 2.3-6, 2.3-7, 2.3-8, 3.4-1, 3.4-2,3.5-7, 3.5-9, 3.5-11, 3.7-1,3.17-1 and 4.5-13.

By: h Michael B. Roche Vice President and Director Oyster Creek Sworn to and Subscribed before me this. day of April 15,1999.

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Geraldine E. Lesin Notary Public GEFW. DINE E. LEVIN NOTARyMSUC0FMN mgc..y. ;w 3 t

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9904210004 990415 hDR ADOCK 05000219 PDR .-

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UNITED STATES OF AMERICA

.- NUCLEAR REGULATORY COMMISSION t

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IN TiiE MATTER OF )

DOCKET NO. 50-219 GPU NUCLEAR, INC. )

CERTIFICATE OF SERVICE This is to certify that a copy ofTechnical Specification Change Request No. 267 for the Oyster Creek Nuclear Generating Station Technical Specifications, filed with the U.S.

Nuclear Regulatory Commission on April 15, 1999 , has this day of April 15. 1999 , been served on the Mayor of Lacey Township, Ocean .

County, New Jersey by deposit in the U.S. mail, addressed as follows:

The lionorable William J. Boehm Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731 By: h Michael B. Roche Vice President & Director Oyster Creek l

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TECilNICAL SPECIFICATION ClIANGE REQUEST (TSCR) NUMBER 267 GPU Nuclear requests that the following replacement pages be inserted into the existing Technical Specifications:

Replace existing pages 1.0-3,1.0-4, 2.3-3, 2.3-4, 2.3-5, 2.3-6, 2.3-7, 3.4- 1, 3.4-2,  ;

3.5-7,3.5-9,3.5-11,3.7-1,3.17-1 and 4.5-13 with the attached replacement pages

' l .0-3,1.0-4, 2.3-3, 2.3-4, 2.3-5, 2.3-6, 2.3-7, 2.3-8, 3.4-1, 3.4-2, 3.5-7, 3.5-9, 3.5-11,3.7-1,3.17-1 and 4.5-13. l

11. ' REASON FOR CHANGE l

l As a result of an NRC Engineering Inspection a comprehensive review of the l Oyster Creek Technical Specifications (TS) was undertaken. That review determined that a number of relatively minor changes to the TS should be made to enhance clarity and understanding. The specific changes are listed below:

Page 1.0-3 Clarification added to definition of Secondary Containment Integrity. ,

1 Pagel.0-4 Definition of FDSAR expanded l

Page 2.3-3 The Bases section was separated from this page which is the last page of the specification.

Page 2.3-4 . Two paragraphs, which should have been deleted in an earlier revision, have been deleted and subsequent pagination is affected.

Two paragraphs have been moved from the end of the bases to that location. An unrelated wording change was also made.

Page 2.3-7 In addition to pagination, add a sentence about the relays involved in undervoltage situations.

Page 3.4-1 The phrase "(see Note below)" is deleted as unnecessary and two lines from the top of page 3.4-2 included as "c".

Page 3.4-2 Two lines moved to prior page and designated "c".

Page 3.5-7 LCO statement of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> deleted from Specification 3.5.B.6.a.3 as inconsistent with Specification 3.5.B.7.

Page 3.5-9 Add a bases statement about administrative control over non-automatic primary containment isolation valves.

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l Page 3.5-11 Add a' bases statement about the use of the trunion room door.

Page 3.7-1 Phrase " shutdown position" corrected to shutdown condition.

1 Page 3,17-1 Phrase "the control room HVAC system" corrected to "one control room IIVAC system".

Page 4.5-13 Change the word "off" to "on" I

II.' SAFETY EVALUA flON JUSTIFYING CilANGE These changes are editorial in nature and as such do not impact the safety features of any plant system. The changes are as follows:

Page 1.0-3 Access openings for personnel and equipment passage into the reactor building have the potential to remain open for a I significant period of time. To prevent loss of vacuum from the reactor building, access openings were designed with airlocks. The trunion room door, by design, does not have an airlock because it provides access only to the trunion room and not the remainder of the reactor building.

Furthermore, traffic through the trunion room door is limited and administratively controlled because the room has been designated as a " Locked High Radiation Door".

This clarification specifically states that secondary containment integrity is not affected by momentary opening and closing of this door.

Pagel .0-4 Definition of FDSAR -The definition of the FDSAR was expanded to indicate that there are a total of 79 Amendments included in the documents known collectively as the "FDSAR". This change is simply an editorial clarification and has no impact on safety.

Page 2.3-3 The bases section was separated from the specification. No change was made to the specification.

Page 2.3-4 A previous TSCR added two paragraphs to this bases section. They were meant to replace two other paragraphs but the existing paragraphs were not deleted at that time.

They have now been deleted and the appropriate paragraphs moved. This change and the one listed directly above

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affect the pagination of the remaining pages of the Bases.

< . A minor wording change was also added.

1 Page 2.3-7 In addition to a pagination change, a sentence was added to clarify that there are two sets of undervoltage relays one of which concerns loss of voltage and the second concems degraded voltage. This change adds additional wording to the Bases to enhance clarity with no impact on safety.

Page 3.4-1 Specification 3.4.A.3 contains the phrase "(see Note j below)". There is, however, no Note. Revision 0 of TSCR 160 did contain a Note and the parenthetical reference. l After a substantial period of time and correspondence Revision I was submitted without the Note or the reference and Amendment 153 was issued accordingly. For a subsequent submittal, the reference was inadvertently inserted. Deletion of the phrase has no safety effect.

In addition, two lines from the top of page 3.4-2 have been relocated to page 3.4-1. They are a continuation of Specification 3.4.A.4 but are not related to segment "b" and, therefore, have been designated as "c". This is an

editorial change that does not add or delete requirements.

Page 3.5-7 Specification 3.5.B.6.a.(3) contains an action statement l describing conditions to be attained within a 36 hour4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> period. Specification 3.5.B.7 requires that if Specifications l 3.5.B.5 and 3.5.B.6 are not met, the reactor must be placed in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This discrepancy has existed since the initial issuance of the TS.

By deleting the phrase, the action statement in Specification 3.5.B.7 would be in effect if the situation were to arise and that action statement is the more conservative of the two.

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Page 3.5-9 The Bases of Specification 3.5 were modified by l Amendment 196 which deleted a Table of PCIVs. The fact that non-automatic PCIVs are administratively controlled was not explicitly addressed at that time. The controls have been in place and are not reduced by this statement.

Page 3.5-11 The Bases now reflect that opening and closing the trunion room door does not violate secondary containment integrity.

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Page 3.7-1 Specification 3.7.B contains the phrase shutdown

. .- " position" which has been corrected to shutdown

" condition". This is an editorial change that does not add or delete tequirements. Therefore, it does not affect safety.

I Page 3.17-1 Specification 3.17.B contains the phrase "the control room HVAC system". There are two such systems and Specification 3.17.C concerns "both" being inoperable.

The actions required by Specification 3.17.B are less severe than those required by 3.17.C. From the context it is clear that 3.17.B refers to one control room IIVAC system being l inoperable. The change does not add or delete l l requirements.

l l Page 4.5-13 In the Bases of Specification 4.5, there is a description of l the position indicating lights during the monthly exercise of i drywell-suppression pool vacuum breakers. When the l valve is Open the Green lights are Off and the Red lights are On. This is misstated in the Bases and the Red lights are described as Off. This change corrects the description

! of the indication from "Off" to "On". The position l indicators are not modified by this change.

l. III. NO SIGNIFICANT HAZARDS DETERMINATION l

GPU Nuclear has determined that this TSCR poses no significant hazard as defined by 10 CFR 50.92,

1. The proposed changes are relatively minor in nature and are proposed to enhance clarity and understanding. None of the changes have any impact

( on safety and there is no change to an operating parameter of any system, E

component or structure. Therefore, the probability of occurrence or the consequences of an accident previously evaluated in the SAR will not increase as a result of these changes.

2. The proposed changes are relatively minor in nature and are proposed to enhance clarity and understanding. None of the changes have any impact on safety and there is no change to an operating parameter of any system, component or structure. Therefore, the proposed activity does not create the possibility for an accident or malfunction of a different type than any previously identified in the SAR.

3. The proposed changes do not involve a reduction in the margin of safety.

The changes are primarily administrative and are proposed to enhance l

clarity and understanding. They do not modify an operating parameter of any system, component or structure Therefore, there is no reduction in j the margin of safety.

II. ' IMPLEMENTATION GPU Nuclear requests that this amendment be effective upon issuance.

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