ML20213G865
| ML20213G865 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/07/1986 |
| From: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20213G786 | List: |
| References | |
| NUDOCS 8611180375 | |
| Download: ML20213G865 (9) | |
Text
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OYSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE N0. DPR-16 Technical Specifications Change Request No. 155 Docket No. 50-219 Applicant submits by this Technical Specification Change Request No.155 to the Oyster Creek Nuclear Generating Station Technical Specifications, modified pages 3.12-4 through 3.12-12, 4.12-5, and 4.12-6.
'1 By.
Peter u. Fiedler Vice President & Director Oyster Creek Sworn to and subscribed before me this day of N#0&>tMtr/,1986.
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Notary Public of New Jersey Expiration Date: 4 - #. 9/
8611180375 861107 PDR ADOCK 05000219 P
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF)
DOCKET NO. 50-219 GPU NUCLEAR CORPORATION)
CERTIFICATE OF SERVICE This is to certify that a copy of Technical Specification Change Request No. !s5 for the Oyster Creek Nuclear Generating Station Technical Specifications, filed with the United States Nuclear Regulatory Commission on November 7
, 1986, has this day of November 7
, 1986, been served on the Mayor of Lacey Township, Ocean County, New Jersey by deposit in the United States mail, addressed as follows:
The Honorable Christopher Connors Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731 fL A. h By A7 'e ?
Peter I. 77TUTer Vice President and Director Oyster Creek DATED:
November 7, 1986 (0240A)
GPU Nuclear Corporation Nuclear
- n:r388 Forked River, New Jersey 08731-0388 609 9~ 1-4000 Writer's Direct Dial Number:
November 7, 1986 The Honorable Christopher Connors Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731
Dear Mayor Connors:
Enclosed herewith is one copy of the Technical Specification Change Request No.155 for the Oyster Creek Nuclear Generating Station Operating License.
This document was filed with the United States Nuclear Regulatory Commission on November 7
, 1986.
Very truly yours, Pe dier Vice President and Director Oyster Creek PBF:GB: dam (0240A)
Enclosures GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
)
0YSTER CREEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE N0. DPR-16 DOCKET NO. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST NO.155 Applicant hereby requests the Commission to change Appendix A of the above-captioned license as follows:
1.
Sections to be changed a.
Section 3.12 and Tables 3.12-1 through 3.12-5; add Table 3.12-6 b.
Section 4.12; add Table 4.12-1 2.
Extent of Changes a.
Section 3.12 is revised to include operability requirements for the Alternate Shutdown Facility Instrumentation. Tables 3.12-1 through 3.12-5 are revised to (1) incorporate new and modified fire detection / suppression systems; and (2) incorporate administrative changes to fire area / zone designations.
b.
Section 4.12 is revised to include surveillance requirements for the Alternate Shutdown Facility Instrumentation. Table 4.12-1 establishes a list of instrumentation and surveillance intervals.
3.
Changes Requested Replace old pages 3.12-4 through 3.12-11, and 4.12-5 with the new pages attached. Add new pages 3.12-12 and 4.12-6.
4.
Discussion These changes incorporate plant modifications that have occurred prior to and during the llR outage. Changes are requested to incorporate fire detection / suppression systems installed for the new cable spread room and cable bridge tunnels; the Alternate Shutdown Facility installed to comply with 10CFR50, Appendix R; modifications to the existing fire detection / suppression systems resulting from plant configuration changes; and administrative changes resulting from changes to the Fire Hazards Analysis.
The changes have been evaluated pursuant to 10CFR50.91 with regard to Significant Hazards.
It has been determined that the changes requested do not represent a significant hazard.
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O Oyster Creek Nuclear Generating Station Technical Specification Change Request #155 No Significant Hazards Detemination 1.0 Introduction GPUN has evaluated the proposed change to the Technical Specifications to detemine whether a significant hazards consideration exists.
2.0 Proposed Changes The proposed changes to the Technical Specifications incorporate new requirements related to the Alternate Shutdown Facility being installed during the current refueling outage in order to comply with the requirements of 10CFR50, Appendix R.
Additional changes are requested to reflect changes in plant fire protection features which have occurred due to configuration changes at the plant. Specifically, the requested changes are as follows:
2.1 Add sections 3.12.I/4.12.I and Tables 3.12-6/4.12-1, the Limiting Conditions of Operation (LCO) and the Surveillance Requirements for the operability of the Alternate Shutdown Facility.
2.2 Revise Table 3.12-1 " Fire Detection Instrumentation" to include new detectors which have been added, new fire area / zone designations, and new detection systems.
2.3 Revise Table 3.12-2 " Spray / Sprinkler Systems" to include new fire suppression systems and new fire area / zone designations.
2.4 Revise Table 3.12-3 " Hose Stations" and Table 3.12-5 " Hydrants and Hose Houses" to include new fire area / zone designations.
l 2.5 Revise Table 3.12-4 "Halon Systems" to include changes in the 480 Volt Switchgear Room Halon System and new fire area / zone designations.
3.0 Basis for No Significant Hazards Determination l
Each of the changes described above has been evaluated using the standards presented in 10CFR50.92.
The results of this evaluation are as follows:
3.1 Section 3.12.I/4.12.I; Table 3.12-6 and 4.12-1 (1) The proposed change will not involve a significant increase in the probability or consequences of an accident previously evaluated. The Alternate Shutdown Facility is being installed in compliance with 10CFR50, Appendix R to provide an alternate means of achieving and maintaining safe reactor shutdown in the unlikely event of a fire in the Control Room or associated Cable Spreading rooms. The Alternate Shutdown Facility has l
been designed so as to eliminate any impact on the probability 1
or consequences of other accidents evaluated for the Oyster Creek Nuclear Generating Station (0CNGS).
Isolation and electrical separation is provided in the Alternate Shutdown Facility by providing key locked switches and electrical circuit isolators to assure that normal and emergency plant operations (other than fire) are unaffected by the Alternate Shutdown Facility. Operation of the facility during a fire condition is accomplished by operation of the key locked switches which transfers control functions to the Alternate Shutdown Facility while disconnecting and isolating these functions in the area affected by the fire. The Alternate Shutdown Facility design was reviewed and approved by the NRC staff in a letter from J. A. Zwolinski to P. B. Fiedler dated March 24,1986.
(2) The proposed change will not create the possibility of a new or different kind of accident from any accident previously analyzed. The Alternate Shutdown Facility provides a similar means of control for achieving safe shutdown as that which 1
could be accomplished from the control room. The facility utilizes existing plant systems and established design 3
l capabilities. The isolation and electrical separation provided assures that operation from the control room will be unaffected during nonnal or emergency (other than fire) conditions. Where the Alternate Shutdown Facility interfaces with safety systems qualified electrical isolators are provided or the interfacing circuits and equipment is designed to safety grade standards.
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(3) The proposed change will not involve a significant reduction in the margin of safety. The isolation and electrical separation of the Alternate Shutdown Facility assures the existing capabilities are retained to mitigate and/or prevent accidents as that which existed prior to installation of the Alternate Shutdown Facility.
Installation of this facility l
increases the margin of safety by providing a means to improve safe shutdown capability in the event of fire in the control j
room or cable spread rooms.
I 3.2 Table 3.12-1 i
j (1) The proposed change will not involve a significant increase in l
the probability or consequences of an accident previously l
evaluated. Additional fire detectors will be added to existing fire detection systems to provide coverage for safety l
related and safe shutdown related cabling. The change also includes new detection systems installed for the upper cable i
spread room and cable bridge tunnels that were previously installed. These additions have been designed consistant with similar fire protection features provided in other areas of the plant and in accordance with the applicable requirements l
of 10CFR50, Appendix R and other regulatory guidance. The fire detectors and fire detection systems alert operators to a possible fire condition and in some cases initiate fire suppression systems. Protection of safety related equipment from inadvertant operation of fire suppression systems is i
provided where necessary.
Pariedic updates of the plant Fire Hazards Analysis (FHA) have resulted in establishing new fire area / zone designations to more accurately identify the characteristics of these areas.
These changes are administrative in nature and do not effect plant nomal or emergency operations.
(2) The proposed change will not create the possibility of a new or different kind of accident from any accident previously analyzed. Additional fire detectors will be added to existing fire detection systems to provide coverage for safety related and safe shutdown related cabling. This change also includes new detection systems installed for the upper cable spread room and cable bridge tunnels that were installed prior to llR. These additions have been designed consistant with similar fire protection features provided in other areas of the plant and in accordance with the applicable requirements of 10CFR50, Appendix R and other regulatory guidance. The fire detectors and fire detection systems alert operators to a possible fire condition and in some cases initiate fire 1
suppression systems. Protection of safety related equipment from inadvertant operation of fire suppression systems is provided where necessary.
Periodic updates of the plant Fire Hazards Analysis (FHA) have resulted in establishing new fire area / zone designations to more accurately identify the characteristics of these areas.
These changes are administrative in nature and do not effect plant normal or emergency operations.
(3) The proposed change will not involve a significant reduction in the margin of safety. New fire detectors added to existing fire detection systems and the new detection systems are designed to the same requirements and criteria as existing fire detection systems throughout the plant. These additions improve fire detection capabilities and maintain the existing margin of safety. The fire area / zone designation changes have no effect on plant operations nor fire suppression capability.
3.3 Table 3.12-2 1
(1) The proposed change will not involve a significant increase in the probability or consequences of an accident previously evaluated. The water suppression systems provided for the upper cable spread room and cable bridge tunnels are designed and installed consistent with similar systems in other plant i
areas and in accordance with 10CFR50, Appendix R and other -
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regulatory guidance. The application of water to the cables used in the plant does not result in cable degradation.
i Provisions have been made to protect safety related equipment from the effects of inadvertant operation of suppression systems and water runoff.
Periodic updates of the plant Fire Hazards Analysis (FHA) have resulted in establishing new fire area / zone designations to more accurately identify the characteristics of these areas.
These changes are administrative in nature and do not effect l
plant nomal or emergency operations.
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(2) The proposed change will not create the possibility of a new or different kind of accident from any accident previously analyzed. The water suppression systems provided for the upper cable spread room and cable bridge tunnels are designed and installed consistent with similar systems in other plant areas and in accordance with 10CFR50, Appendix R and other regulatory guidance. The application of water to the cables used in the plant does not result in cable degradation, j
Provisions have been made to protect safety related equipment from the effects of inadvertant operation and water runoff.
Periodic updates of the plant Fire Hazards Analysis (FHA) have resulted in establishing new fire area / zone designations to more accurately identify the characteristics of these areas.
These changes are administrative in nature and do not effect plant nonnal or emergency operations.
i j.
(3) The proposed change will not involve a significant reduction in the margin of safety. The new fire suppression systems are designed and installed to the same requirements and criteria as existing suppression systems throughout the plant. The addition of these systems maintains the margin of safety established. The fire area / zone designation changes have no effect on plant operations nor fire suppression capability.
3.4 Table 3.12-3 and Table 3.12-5 (1) The proposed change will not involve a significant increase in the probability or consequences of an accident previously l:
ev'aluated; and (2) The proposed change will not create the possibility of a new or different kind of accident from any accident previously analyzed; and (3) The proposed change will not involve a significant reduction in the margin of safety as follows:
The proposed changes only reflect administrative revisions to fire area / zone designations. The revised designations clarify fire area / zone locations and characteristics. These changes are adninistrative in nature and da not materially affect any plant systems, operation, or analyses.
3.5 Table 3.12-4 (1) The proposed changes will not involve a significant increase in the probability or consequences of an accident previously evaluated.
In order to comply with 10CFR50, Appendix R, the 480 volt switchgear room will be divided into two (2) fire zones separated by a one hour fire barrier. The existing halon system for this area will be modified to provide independent fire suppression capability for each zone in this area. The mudification has been designed in accordance with applicable requirements and design criteria that was l
yh 4
previously invoked for t$1s area prior to the installation of the fire barrier. Therefore, this modification does not effect the analysis of any accidents previously evaluated and decreases the consequences of a fire in the 480 volt switchgear room.-
(2) The proposed changes will not create the possibility of a new or different kind of accident from any accident previously analyzed. Ttese changes do riot add nor diminish the level of i
fire safety within the 480 volt switchgear room. The existing systems are being modified to retain compliance with existing requirements and regulatory guidance.
The changes modify the are,a of coverage but do not effect any operational charccteristics or operational parameters. The modification has been designed consistent with similar fire protection features in other areas of the plant.
The changes to fire area / zone designations are administrative in nature and'do not effect any plant systems, operations, or analysis.except that two new zones have been established _to identi.fy additional separati~on of safety related and safe snutdewn systems and compor,ents.
(3) The proposed changes will not involve a significant reduction in the margin of safety.. These changes provide additional-separation of safety related -and safe shutdown systeais/ components while n:aintaiaing the level of fire safety previously existing prior to modification, therefore, the margin of safety has been increased.
Changes to fire area / zone designations do not effect any plant systems, operation, or analpes and have no effect on the margin of safety.
4.0 Conclusion s
Each proposed change has been evaluated in relation to the standards provided in 10CFR50.92. -Ir. e:ch case, the results of this evaluation l
result in a finding that 49 significant hazards exist in relation to the changes requested.
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