ML20214S577
| ML20214S577 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/28/1986 |
| From: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20214S557 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-3.D.3.4, TASK-TM NUDOCS 8612080331 | |
| Download: ML20214S577 (3) | |
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GPU NUCLEAR CORPORATION OYSTER CREEK NUCLEAR GENERATING STATION Provisional Operating License No. DPR-16 Technical Specification Change Request No. 151 Docket No. 50-219 Applicant submits, by this Technical Specification Change Request No.151 to the Oyster Creek Nuclear Generating Station Technical Specifications, a change
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to the Table of Contents, and Sections 3.17, and 4.17.
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By Pe er B. Fi er V e Presi t and Director ster Crc Sworn and Subscribed to before me this ((
dayofA/0/.
1986.
W a./r)si a A Notary Public of NJ Optrahdn Sh l
8612080331 861128 DR ADOCK 0500 9
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3 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the matter of
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Docket No. 50-219 GPU Nuclear Corporation
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CERTIFICATE OF SERVICE This is to certify that a copy of Technical Specification Chance Request No.151 for Oyster Creek Nuclear Generating Station Technical Specifications, filed with the U.S. Nuclear Regulatory Commission on November 28, 1986, has this day of November 28, 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 0
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Pet r B. Fied Vi e Presiden nd Director 0 ster Creek i
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3-GPU Nuclear ga 38 100 Interpace Parkway Mw E
Parsippany. New Jersey 07054 201 263-6500 TELEX 13G-482 Writer's Direct Dial Number November 28, 1986 The Honorable Christopher Connors Mayor of Lacey Township 818 West Lacey Road Forked River, New Jersey 08731
Dear Mayor Connors:
Enclosed herewith is one copy of Technical Specification Change Request No.151 for the Oyster Creek Nuclear Generating Station Operating License.
This document was filed with the United States Nuclear Regulatory Commission on November 28, 1986 ry tr ly yo s,
Y P ter B. Fie 1 r i
ice Presid and Director Oyster Creek PBF/pa 3807f Attachment l
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GPU Nuclear is a part of the General Public Utilities System
" (, ENuclear GPU Nuclear
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201 263-6500 TELEX 136-482 Writer's Direct Dial Number:
November 28, 1986 Mr. Frank Cosolito, Acting Chief Bureau of Radiation Protection Department of Environmental Protection 380 Scotch Road Trenton, New Jersey 08628
Dear Mr. Cosolito:
Subject:
Oyster Creek Nuclear Generating Station Provisional Operating License No. DPR-16 Technical Specification Change Request No. 151 Pursuant to 10CFR50.91(b)(1), please find enclosed a copy of the subject document which was filed with the United States Nuclear Regulatory Commission
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on November 28, 1986
- 4 Very truly ours, j
i3 eter B. F dier Vice Presi ent and Director Oyster Creek PBF/pa 3807f Attachment l
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GPU Nuclear is a part of the General Public Utilities System
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OYSTER OtEEK NUCLEAR GENERATING STATION PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST NO.151 3
l Applicant hereby requests the Commission to change Appendix A to the above captioned license as below, and pursuant to 10CFR50.91, ~an analysis concerning the determination of no significant hazards considerations is also presented:
1 1.
Sections to be Changed Table of Contents; Sections 3.17, and 4.17
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2.
Extent of Change a.
Limiting Conditions for operation are being proposed for the following:
Section 3.17 - Control Room Heating, Ventilating;and Air Conditioning (HVAC) System b.
Surveillance Requirements are being proposed for the following:
c Section 4.17-Control Room HVAC System
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3.
Changes Requested l
The requested changes are shown on attached Technical Specification pages:
11, iii. 3.17-1, and 4.17-1.
4.
Discussion i
By a Confirmatory Order dated March 14, 1983, GPU Nuclear (GPUN) was
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required to have NUREG 0737 Item III.D.3.4, Control Room Habitability, j
fully implemented at the Oyster Creek Nuclear Generating Station (OCNGS) before the restart from the Cycle 11 refueling outage. By a reauest dated e
June 4,1985, GPUN was granted a postponement (Amendment 105) of full implementation until the Cycle 12 outage provided that interim system
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upgrades and accident analyses were completed. These items were completed L
with the final outstanding item being this submittal of appropriate
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technical specifications for the Control Room HVAC system.
l The requirements to be deferred to the Cycle 12 outage to fully implement Control' Room Habitability were the following:
(1)' perform a single i
l failure analysis of the control room ventilation system and provide r
remedial measures, (2) assess existing diesel generator capability to provide backup power to the control room ventilation system and (3) meet i the beta skin dose limits with the final control room ventilation system i design without protective clothing and goggles.
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The control room envelope consists of the control room panel area, the Shift' Supervisor's office, toilet room, kitchen, and cable spreading rooms.
Nomal ventilation is provided by a system utilizing one supply fan with steam coils for heating and a three-stage refrigeration unit for cooling. The ability to recirculate air is provided, with recirculation varying from 0 to 100 percent. A purge mode is provided for operation with 100 percent outside air to prevent the recirculation of smoke in the Control Room and to clear the area of smoke and fumes.
4 The system is normally operated to maintain room air at 75 degrees F.
Under i
. nonnal operation of the turbine generator unit, the system cools during winter
,and summer.
Heat to maintain 70 degrees F in these areas is anticipated to be required only during the winter when the turbine generator is not operating.
Major components of the system are the air conditioning unit and the two heating coils.
The system does not include filters to reduce the intake of radioactivity.
l Upon the receipt of a LOCA or high containment radiation signal in the control l
room, the operators will switch the control room HVAC system to the partial recirculation mode of operation. For this mode of operation, the control. room pressure envelope is held at a minimum of 1/8 inch water gauge positive pressure, and the total measured makeup plus infiltration air flow is 1830 cfm.
The radiological analyses (6/17/85) previously submitted to the staff were based on the original design of the control room.HVAC system. The intent of the original system design was to provide a minimum of 450 cfm infiltration
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for pressurization and air replacment purposes rather than restrict the infiltration to a maximum of 450 cfm.
The three airborne fission product release paths considered were Main Steam Isolation Valve Bypass Leakage, Containment Leakage and Engineered Safety Features Leakage. Since the NRC staff is presently reviewing the iodine source term for the design basis LOCA i
accident, the analyses were restricted to whole body and beta skin doses from noble gases.
The calculations were revised to determine the effect of nigher infiltration i
rates on the 30-day gamma whole-body and beta skin doses to the operators.
l The results are presented below:
Flow Rate 30 day dose (REM)
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(cfm)
Gamma Beta i
1500 3.05 27.9 l
2000 3.07 28.2 Although the infiltration rate had increased by as much as a factor of 4, the doses did not increase in the same proportion. The reason for this is that when the infiltration rate is increased, the exfiltration from the control room envelope increased at the same rate, thereby having only a small effect t
on the isotopic concentrations in the control room at any time over the 30 day i
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period. The revised concentrations produced higher doses to the operators; (1
however, all the doses were.less than the S.R.P. 6.4 limits of 5 rem and 30 rem for gamma and beta doses respectively. Also, the radiological analysis did not rely on the use of goggles or protective clothing to meet the GDC 19 -
beta skin dose guidelines, a Cycle 12 commitment. Therefore, the control room 4
was determined radiologically habitable for 30 days following a design basis.
LOCA.
BecausethecontrolroomHVdCsystemhasnofilterstoreducethe radioactivity following a LOCA, the loss of the control room HVAC does not change the analysis for meeting the GDC 19 criteria on radiation exposure.
l The control room operators have time to manually close dampers to isolate the l
control room and to provide heating or cooling to the control room from other sources, if needed, so that the proposed action does not significantly a
6 increase ~ the consequences of a previously evaluated accident or create a new or different kind of accident.
The effects of natural phenomena in the control room are being excluded from the issue of Control Room Habitability. These effects are being addressed in the Systematic Evaluation Program (SEP) in the following active reviews:
tornado missiles, SEP Topic III-4.A; seismic design considerations, SEP Topic i'
III-6.; wind and tornado loadings, SEP Topic III-2; and flooding potential and protective requirements, SEP Topic II-3.B.
These reviews are discussed in the staff's Integrated Plant Safety Assessment Report for Oyster Creek, NUREG-0822, dated January 1983.
5.
Determination Based upon the hereinbefore discussion, we have evaluated that this change i
request involves no significant hazards considerations.
In summary, we
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have determined that the proposed amendment would not:
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Involve a significant increase in the probability or consequences of:
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an accident previously evaluated;
- The Control Room HVAC system is not an initiator or mitigator of an accident previously analyzed, and therefore does not change the probability or the consequences of any design basis accidents.
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Create the probability of a new or different kind of accident from any accident previously evaluated;
- The Control Room HVAC system is not an initiator of a new or r
i different kind of accident, and therefore does not create the probability of a new or different kind of accident.
3.
Involve a significant reduction in a margin of safety; l
- The Control Room HVAC does not mitigate the consequences of any.
previously analyzed accident, and therefore does not involve any reduction in a margin of safety.
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L' TABLE OF CONTENTS (cont'd) 3.4 Emergency Cooling 3.4-1 3.5 Containment 3.5-1 3.6 Radioactive Effluents 3.6-1 3.7 Auxiliary Electrical Power 3.7-1 3.8 Isolation Condenser 3.8 3.9 Refueling 3.9-1 3.10 Core Limits 3.10-1 3.11 (Not Used) 3.11-1 i
3.12 Fire Protection 3.12-1 3.13 Accident Monitoring Instrumentation 3.13-1 3.14 Solid Radioactive Waste 3.14-1 3.15 Radioactive Effluent Monitoring 3.15-1 i
Instrumentation 3.16 (Not Used) 3.16-1 3.17 Control Room Heating, Ventilating, and 3.17-1
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Air-Conditioning System i
e Section 4 Surveillance Requirements 4.1 Protective Instrumentation 4.1-1 4.2 Reactivity Control 4.2-1 i
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4.3 Reactor Coolant 4.3-1
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4.4 Emergency Cooling 4.4-1 4.5 Containment 4.5-1 i
4.6 Radioactive Effluents 4.6-1 l
4.7 Auxiliary Electrical Power 4.7-1 4.8 Isolation Condenser 4.8-1 4.9 Refueling 4.9-1 4.10 ECCS Related Core Limits 4.10-1 L
4.11 Sealed Source Contamination 4.11-1 4.12 Fire Protection 4.12-1 l
4.13 Accident Monitoring Instrumentation 4.13-1 F
4.14 Solid Radioactive Waste 4.14-1 f
4.15 Radioactive Effluent Monitoring 4.15-1 Instrumentation 4.16 Radiological Environmental Surveillance 4.16-1 4.17 Control Room Heating, Ventilating and 4.17-1 Air-Conditioning System I
Section 5 Design Features I
5.1 Site 5.1-1 1
5.2 Containment 5.2-1 5.3 Auxiliary Equipment 5.3-1 11 I
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,,A-TABLE OF CONTENTS (Cont'd)
Section 6 Administrative Controls 6.1 Responsibility 6-1 6.2 Organization 6-1 6.3 Facility Staff Qualifications-6-6 6.4 Training 6-8 6.5 Review and Audit 6-8 6.6 Reportable Event Action 6-14 6.7 Safety Limit Violation 6-14 6.8 Procedures 6-14 6.9 Reporting Requirements 6-15 6.10 Record Retention 6-19 6.11 Radiation Protection Program 6-20 6.12 (Deleted) 6-20 6.13 High Radiation Area 6-20 6.14 Environmental Qualification 6-21*
6.15 Integrity of Systems Outside Containment 6-21 6.16 Iodine Monitoring 6-22 6.17 Post Accident Sampling 6-22 0
- Issued by NRC Order dated 10-24-80
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3.17-1~
Control Room Heating, Ventilating, and Air-Conditioning System Applicability:
Applies to the operability of the control room heating, ventilating, and air-conditioning (HVAC) system.
Objective:
To ensure the capability of the control room HVAC system to minimize the amount of radioactivity from entering the control room in the event of an accident.
Specification:
A.
The control room HVAC system shall be. operable during all modes of plant operation.
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8.
With the control room HVAC system determined inoperable:
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Manually align the dampers for the partial recirculation mode of operation.
- 2.. Restore the system to operable status within 7 days or prepare and submit a special report to i
the Commission in lieu of any other report required by Section 6.9, within the,next 14 days, outlining the action taken, the cause of the ff inoperability and the plans / schedule for
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restoring the HVAC system to operable status.
Basis:
_The operability of the control room HVAC system ensures i
that the control room will remain habitable for operations personnel during a postulated loss-of-coolant accident.
If the system is found to be inoperable, there is no immediate threat to the control room. The control room personnel have time to manually align the dampers to i
minimize the air inflow to the control room envelope.
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4.17-1 Control Room Heating, Ventilating, and Air-Conditioning System Applicability:
Applies to surveillance requirements for the control room heating, ventilating, and air-conditioning (HVAC) system.
Objective:
To verify the capability of the control room HVAC system to minimize the amount of radioactivity frcm entering the control room in the event of an accident.
Specification:
The control room HVAC system shall be demonstrated operable:
A.
At least once monthly:
by initiating, from the control room, the partial recirculation mode of operation, and by verifying that the system components are aligned such that the system is operating in this mode.
B.
At least once every refueling outage-by verifying that in the partial recirculation mode of operation, the control room and lower cable spreading room are maintained at a positive pressure of.% 1/8 in. WG relative to the outside atmosphere with the total g
flow rate of makeup air plus infiltration air less
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than or equal to 2000 cfm.
Basis:
Periodic surveillance of the control room HVAC system is required to ensure the operability of the system. The operability of the system in conjunction with control room i
design provisions is based upon limiting the radiation exposure to personnel occupying the control room to less than a 30-day integrated gamma dose of 5 rem, and a 30-day integrated beta dose of 30 rem.
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