ML20149F767
| ML20149F767 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 01/04/1988 |
| From: | Hood D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20149F770 | List: |
| References | |
| NUDOCS 8801140328 | |
| Download: ML20149F767 (12) | |
Text
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UNITED STATES y
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DUKE POWER COMPANY DOCKET NO. 50-369 McGt!!RE NUCLEAR STATI6N. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE I
Amendment No.
78 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-9 filed by the Duke Power Company (the licenseel dated July 31, 1987, complies with the standards and re Act of 1954, as amended (the Act) quirements of the Atomic Energy and the Commission's rules and regulations as set forth in 10 CFR Chapter I; 8
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will 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 requirements have been satisfied.
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Accordingly,-the license is hereby amended by page changes to the Technical Specifications as-indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:
(2)TechnicalSpecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 78, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR PEGULATORY COMMISSION Darl S. Hood, Acting. Director Project Directorate 11-3 Division of Reactor Projects-I/II
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Attachment:
Technical Specification Changes Date of Issuance:
January 4, 1988 4
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NUCLEAR REGULATORY COMMISSION
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DUKE POWER COMPANY DOCKET N0. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendrrent No. 59 License No. NPF-17 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-17 filed by the Duke Power Company (the licensee) dated July 31, 1987,
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complies with the standards and re Act of 1954, as amended (the Act) quirements of the Atomic Energy and the Comission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 l
in compliance with '.he Comission's regulations set forth in 10 CFR l
Chapter I; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulstions and all applicable requirements have been satisfied.
- - 2.'
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:
(2)_' Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 59, are hereby incorporated into the. license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COW 11SSION M
Darl S. Hood, Acting Director Project Directorate II-3 Division of Reactor Projects-I/II
Attachment:
Technical Specification Changes Date of Issuance:
January 4, 1988 I.
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ATTACHMENT TO LICENSE AMENDMENT NO. 78 FACILITY OPERATING LICENSE N0. NPF-9 DOCKET N0. 50-369 AND TO LICENSE AMENDMENT N0. 59 FACILITY OPERATING LICENSE N0. NPF-17 DOCKET N0. 50-370 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding over-leaf pages are also provided to maintain document completeness.
Amended Overleaf Page Page 3/4 7-11 3/47-11a(new) 3/4 7-12 B 3/4 7-3 B 3/4 7-3a B 3/4 7-3b (new)
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1
PLANT SYSTEMS 3/4.7.4 NUCLEAR SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4 At least two independent nuclear service water loops shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
With the unit specific portion of only one nuclear service water loop a.
per unit OPERABLE, restore both unit specific loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or place the affected unit at least in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With only one of the shared portions as defined by Figure 3/4 7-1 of the Unit 1 and Unit 2 nuclear service water loops OPERABLE, restore the shared portion of the loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or place both units in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.4 At least two nuclear service water loops per unit shall be demonstrated l
OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) servicing safety-related equipment that is not locked, sealed, or otherwise secured in position is in its correct position; and b.
At least once per 18 months during shutdown, by verifying that:
1)
Each automatic valve servicing safety-related equipment actuates to its correct position on a Safety Injection test signal, and 2)
Each nuclear service water pump starts automatically on a Safety Injection and Station Blackout test signal.
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McGUIRE - UNITS 1 and 2 3/4 7-11 Amendment No. 78 (Unit 1)
Amendment No. 59 (Unit 2) l l
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PLANT SYSTEMS
'3/4.7.5 'STANDBYNUCLEARSERVICEhATERPOND LIMITING CONDITION FOR OPERATION 3.7.5 The standby nuclear service water pond shall be OPERABLE with:
a.
A minimum water level at or above elevation 739.5 feet Mean Sea Level, USGS datum, and b.
An average water temperature of less than or equal to 78*F at elevation 700 feet in the intake structure.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
(Units 1 and 2)
With the requirements of the above specification not satisfied, be in at least
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HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
t-SURVEILLANCE REQUIRMENTS 4.7.5 The standby nuclear service water pond shall be determined OPERABLE:
a.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the water level to be within its limit, b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during the months of July, August and September by verifying the water temperature to be within its limit, and c.
At least once per 12 months by visually inspecting the dam and verifying no abnormal degradation, erosion, or excessive seepage.
McGUIRE - UNITS I and 2 3/4 7-12 s
PLANT SYSTEMS BASES 3/4.7.1.4 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensures that n more than one steam generator will blow down in the event of a steam line rupture.
This restriction is required to:
effects of the Reactor Coolant System cooldown associated with the blow and (2) limit the pressure rise within containment in the event the steam line rupture occurs within containment.
The OPERABILITY of the main steam isolation valves within the closure times of the Surveillance Requirements are consistent with the assumptions used in the accident analyses.
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure-induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits.
The limitations of 70 F and 200 psig are based on a steam generator RT f 10 F and are sufficient to prevent brittle fracture.
NDT 3/4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the Component Cooling Water System ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions.
The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.
3/4.7.4 NUCLEAR SERVICE WATER SYSTEM The OPERABILITY of the Nuclear Service Water System ensures that sufficient cooling capacity is available for continued operation of safety-related equip-ment during normal and accident conditions.
The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident conditions within acceptable limits.
Periodic flow balance tests, delta-P tests, and heat balance tests are performed as required to assure adequate flow to all essential heat exchangers for which flow instrumentation is provided.
Portions of the Nuclear Service Water System are common to both units.
These shared portions of the system are indicated on Figure 3/4 7-1 and common valves are listed in Table B 3/4 7-1 and include common suction piping and cross connect piping as indicated on the figure.
With the exception of ORN-1 all shared valves receive emergency power from two essential motor control centers (IEMXH, 2EMXH).
ORN-1 is normally open with the power removed.
Motor Control Center (MCC) 1EMXH can be powered by either Unit 1 or Unit 2 A Train Emergency D/G's via their associated switohgear.
Motor Control Center 2EMXH can be powered by either Unit 1 or 2 B Train Emergency D/G's via their associated switchgear.
McGuire - UNITS 1 and 2 8 3/4 7-3 Amendment No. 78 (Unit 1)
Amendment No. 59 (Unit 2)
e PLANT SYSTEMS BASES 3/4.7.4 NUCLEAR SERVICE WATER SYSTEM (Continued)
The four loops (two per unit) ensure redundancy and the availability of cooling to both units, even if a single failure were to render two loops in-operable.
(Such a failure would involve train A of both units or train B of both units, not both trains of the same unit).
The Action statements are sep-arated to clarify that portions of the systems are shared though the majority of each of the four loops is independent.
In the event of a safety injection or blackout signal on either unit, train A of both units will align to Lake Norman and train B of both units will align to the SNSWP.
Additionally, all train A to train B cross-connects will close on both units as will non-safety to safety related cross-connects.
These actuations assure independence of the loops and the required redundancy under design basis conditions.
3/4.7.5 STANDBY NUCLEAR SERV 1.E WATER POND The limitations on the standby nuclear service water pond level and temperature ensure that sufficient cooling capacity is available either to:
(1) provide normal cooldown of the facility, or (2) mitigate the effects of accident conditions within acceptable limits.
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McGuire - UNITS 1 and 2 B 3/4 7-3a Amendment No. 78 (Unit 1)
Amendment No. 59 (Unit 2)
I' TABLE B 3/4 7-1 UNITS 1 AND 2 NUCLEAR SERVICE WATER SYSTEM SHARED VALVES ORN-1 LOW LEVEL-IhTAKE SUP TO RN ORN-28 TRAIN A RC SUPPLY ORN-3A,C TRAIN A RC SUPPLY ORN-4A C TRAIN B RC SUPPLY ORN-5B TRAIN B RC SUPPLY ORN-7A,C TRAIN A SNSWP SUPPLY ORN-98 TRAIN B SNSWP SUPPLY ORN-10A,C TRAIN B LLI SUPPLY ORN-11B TRAIN B LLI SUPPLY ORN-12A,C TRAIN A LLI SUPPLY ORN-13A TRAIN A LLI SUPPLY ORN-14A TRAIN A SUCT X-CONNECT ORN-15B TRAIN B SUCT X-CONNECT ORN-147A,C TPAIN A DISCH TO RC ORN-148A,C TRAIN A DISCH TO RC l
ORN-149A TRAIN A DISCH TO RC ORN-150A,C TRAIN A DISCh X-CONNECT ORN-151B TRAIN B DISCH X-CONNECT ORN-1528 TRAIN B DISCH TO SNSWP ORN-283A,C TRAIN B DISCH TO RC ORN-284B TRAIN B DISCH TO RC 1
1 ORN-301A,C RV SUPPLY FROM LLI l
ORN-3028 RV SUPPLY FROM LLI McGuire - UNITS 1 and 2 B 3/4 7-3b Amendment No.78 (Unit 1)
Amendment No.59 (Unit 2) l l
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BASES l
STANDBY NUCLEAR SERVICE WATER POND (Continued) l l
The limitations on minimum water level and maximum temperature are based l
on providing a 30-day cooling water supply to safety-related equipment without exceeding their design basis temperature and is consistent with the recommend-ations of Regulatory Guide 1.27, "Ultimate Heat Sink for Nuclear Plants,"
March 1974.
The Surveillance Requirements specified for the dam inspection will conform to the recommendations of Regulatory Guide 1.127, Revision 1, March 1978 3/4.7.6 CONTROL AREA VENTILATION SYSTEM The OPERABILITY of the Control Area Ventilation System ensures that:
(1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system, and (2) the control room will remain habitable for operations personnel during and following all credible accident conditions.
Cumulative operation of the system with the heaters on for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31-day period is sufficient to '/ educe the buildup of moisture on the adsorbers and HEPA filters.
The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent.
This limitation is consistent with the requirements of General Design Criterion 19 of Appendix A,10 CFR 50.
ANSI H510-1975 will be used as a procedural guide for surveillance testing.
3/4.7.7 AUXILIARY BUILDING FILTERED VENTILATION EXHAUST SYSTEM The OPERABILITY of the Auxiliary Building Filtered Ventilation Exhaust Sy', tem ensures that radioactive materials leaking from the ECCS equipment
- ithin the auxiliary building following a LOCA are filtered prior to reaching the environment.
The operation of this system and the resultant effect on offsite dosage calculations were assumed in the accident analyses.
ANSI N510-1975 will be used as a procedural guide for surveillance testing.
The methyl iodide penetration test criteria for the carbon samples have been made more restrictive than required for the assumed iodine removal in the accident analysis because the humidity may be greater than 70% under normal operating conditions.
McGUIRE - UNITS 1 and 2 8 3/4 7-4 s