ML20206J286
| ML20206J286 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/31/1987 |
| From: | Grotenhuis M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206J289 | List: |
| References | |
| NUDOCS 8704160058 | |
| Download: ML20206J286 (7) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION 3
o WASHINGTON, D. C. 20555
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GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT C0"PANY DOCKET NO. 50-219 OYSTER' CREEK NUCLEAR GENERATING STATION AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No.115 License No. DPR-16 1.
The Nuclear Pegulatory Commission (the Comission) has found that:
A.
The application for amendment by GPU Nuclear Corporation and Jersey Central Power and Light Company (the licensees) dated November 28, 1986, complies with the standards and reouire-ments of the Atomic Energy Act ~of 1954,\\as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment wfil not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable reouirements have been satisfied.
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Provisional Operating License No. DPR-16 is hereby amended to read as follows:
(2) -Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.115, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION pge/gj(',
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, Marshall Grotenhuis, Acting D_irector BWR Project Directorate #1 Division of BilR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 31, 1987
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ATTACPPENT TO LICENSE AMENDMENT NO.iig
.4 PROVISIONAL OPERATING LICENSE NO. DPR-16 I
[0CKETNO.50-219 r,
t Revise the Appendix A Technical Speci"ications by removing the pages identified j,
below and inserting the attached pages. The revised pages are identified by the captioned arendment number and contain vertical lines indicating the 7,
area of change.
REMOVE INSERT 11 11 i@
iii i
3.17-1 4.17-1
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TABLE OF CONTENTS (cont'd)
Section 3 Limiting Conditions for Operation 3.0 Limiting Conditions for Operation (General) 3.0-1 3.1 Protective Instrumentation 3.1-1
, $; 3. 2 Reactivity Control 3.2-1 3.3 Reactor Coolant 3.3-1 3.4 Emergency Cooling 3.4-1 3.5 Containment 3.5-1
- 3. 6 Radioactive Effluents 3.6-1 y
3.7 Auxiliary Electrical Power 3.7-1 3.8 Isolation Condenser 3.8-1
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- 3. 9 Refueling 3.9-1 3.10 Core Limits 3.10-1 3.11 (Not Used)
.3.11-1 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 Instrumentation 3.15-1 3.16 (Not Used) 3.16-1 3.17 Control Room Heating, Ventilating and Air Conditioning System 3.17-1 Section 4 Surveillance Requirements 4.1 -
Protective Instrumentation 4.1-1 4.2 Reactivity Control 4.2-1 4.3 Reactor Coolant 4.3-1 4.4 Emergency Cooling 4.4-1 4.5 Containment 4.5-1 4.6 Radioactive Effluents 4.6-1 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 4.11 Sealed Source Contamination 4.11-1 4.12 FjreProtection 4.12-1 4.13 Accident Monitoring Instrumentation 4.13-1 4.14 Solid Radioactive Waste 4.14-1 4.15 Radioactive Effluent Monitoring Instrumentation 4.15-1 4.16 Radiological Environmental Surveillance 4.16-1 4.17 Control Room Heating, Ventilating and Air Conditioning l
System 4.17-1
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OYSTER CREEX ii Amendment No.: 54, 59, 84, 97, 108, II5
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TABLE OF CONTENTS (cont'd)
Section 5 Design Features 5.1 Site 5.1-1 5.2 Containment 5.2-1 5.3 Auxiliary Equipment 5.3-1 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 6-15 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 6-21 6.17 Post Accident Sampling 6-22 6.18 Process Control Plan 6-22 6.19 Offsite Dose Calculation Manual 6-22 6.20 Major Changes to Radioactive Waste Treatment Systems 6-23
- Issued by NRC Order dated 10-24-80 OYSTER CREEK iii Amendment No.: 84, 97, 98, 108, 115'
3.17 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 assure 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.
B.
With the control room HVAC system determined inoperable:
1.
Manually align the dampers for the partial recircula-tion mcde of operation.
2.
Restore the system to operable status within 7 days or prepare and submit a special report to 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 inoperability and the plans / schedule for restoring the HVAC system to operable status.
Basis:
The operability of the control room HVAC system ensures 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 con-trol room.
The control room personnel have time to manually align the dampers to minimize the air inflow to the control room envelope.
l OYSTER CREEK 3.17-1 Amendment No.: 115 l
4.17 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 from 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 flow rate of makeup air plus infiltration air less than or equal to 2000 cfm.
Basis:
Periodic surveillance of the control room HVAC system is re-quired to ensure the operability of the system. The operability of the system in conjuction with control room 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.
0YSTER CREEK 4.17-1 Amendment No.: 115
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