ML20235X770
| ML20235X770 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 03/02/1989 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235X772 | List: |
| References | |
| NUDOCS 8903130621 | |
| Download: ML20235X770 (12) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION E
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DUKE POWER COMPANY DOCKET NO. 50-369 McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 93 License No. NPF-9 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating Licensc No. NPF-9 filed by the Duke Power Company (the licensee) dated January 27, 1988, and supplemented April 26, June 21 and August 25, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; 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 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 Connission's regulations and all applicable requirements have been satisfied.
8903130621 890302 _
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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) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 93, 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 COMfilSSION original signed By:
David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-1/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes j
l Date of Issuance: March 2, 1989 l
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UNITED STATES j
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DOCKET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. NPF-17 1.
The Nuclear Regulatory Commission (the Commission) 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 January 27, 1988, and supplemented April 26, June 21, and August 25, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; 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 set forth in 10 CFP.
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-17 is hereby amended to read as follows:
(2) Technical Specifications h
The Technical Specifications contained in Appendix A, as revised through Amendment No. 74, 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 COMMISSION original Signed By:
David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: March 2, 1989 0FFICIAL RECORD COPY
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4 ATTACHMENT TO LICENSE AMENDMENT NO. 93 0
FACILITY OPERATING LICENSE NO. NPF-9 DOCKET N0. 50-369 i
AND TO LICENSE AMENDMENT NO. 74 FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 i
Replace the following pages of-the Appendix "A" Tec.hnical 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.
j Amended Page Overleaf Page XII l
3/4 7-44 3/4 7-43 l
3/4 7-45 3/4 7-46
'B 3/4L7-8 B 3/4 7-7 4
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1 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7.5 STANDBY NUCLEAR SERVICE WATER P0ND.......................
3/4 7-12 3/4.7.6 CONTROL AREA VENTILATION SYSTEM..........................
3/4 7-13 3/4.7.7 AUXILIARY BUILDING FILTERED VENTILATION EXHAUST SYSTEM...
3/4 7-16 3/4.7.8 SNUBBERS.................................................
3/4 7-18 TABLE 3.7-4a SAFETY-RELATED HYDRAULIC SNUBBERS (UNITS 1 AND 2)....
3/4 7-23 TABLE 3.7-4b SAFETY-RELATED MECHANICAL SNUBBERS (UNITS 1 AND 2)...
3/4 7-26 FIGURE 4.7-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST...........
3/4 7-29 3/4.7.9 SEALED SOURCE CONTAMINATION..............................
3/4 7-30 R
3/4.7.10 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System............................
3/4 7-32 Spray and/or Spri nkl er Systems...........................
3/4 7-34 Halon Systems.............................................
3/4 7-36 Fire Hose Stations........................................
3/4 7-37 TABLE 3.7-5 FIRE H0SE STATIONS.....................................
3/4 7-38 3/4.7.11 FIRE BARRIER PENETRATIONS.................................
3/4 7-40 3/4/7.12 AREA TEMPERATURE M0NITORING...............................
3/4 7-42 TABLE 3.7-6 AREA TEMPERATURE M0NITORING............................
3/4 7-43 3/4.7.13 GROUNDWATER LEVEL.........................................
3/4 7-44 i
TABLE 3.7-7 AUXILIARY BUILDING GROUNDWATER LEVEL MONITORS..........
3/4 7-45 3/4.9 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES 0perating......................
3/4 8-1 TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE......................
3/4 8-8 McGuire - Units 1 and 2 XII Amendment No.93(Unit 1)
Amendment No.74 (Unit 2)
TABLE 3.7-6 AREA TEMPERATURE MONITORING AREA TEMPERATURE LIMIT (*F) 1.
Containment Spray Pump Rooms - Unit 1 145
- Unit 2 145 2.
. Miscellaneous Terminal Cabinets a.
T3208-209 (Turbine Ridg. - Unit 1)
'150 b.
TB1208-1209 (TurH ne 81dg. - Unit 2) 150 c.
TB496 (Fuel Bldg. - Unit'1) 150 d.
TB1496 (Fuel Bldg. - Unit 2)
-150 3.
' Residual Heat Removal Pump Rooms - Unit 1
.145
- Unit 2 145 4.
Diesel Generator Rooms - Unit 1 125
- Unit 2 125 l
S.
-Spent Fuel Pool Cooling Pump Room - Unit 1 145
- Unit 2 145 1
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McGUIRE - UNITS 1 and 2 3/4 7-43
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3/4.7.13 GROUNDWATER LEVEL LIMITING CONDITION FOR OPERATION G
3.7.13 The groundwater level shall be maintained at elevations less than the values in Table 3.7-7 for the five (5) Auxiliary Building monitors listed in Table 3.7-7.
APPLICABILITY: At all times.
ACTION:
For Units 1 and 2.
If groundwater level for any three (3) of the five (5) monitors is above.the values shown in Table 3.7-7, take the following actions:
1.
Within one hour, reduce the groundwater level to below the values shown in Table 3.7-7; or, 2.
Be in'at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and H0T SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 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 4.7.13.1 During each shift,- the groundwater level shall be demonstrated to be within the values of Table 3.7-7 by the absence of alarms or by visual observation of the monitor level gauge.
4.7.13.2 Each groundwater level monitor instrument / loop for locations listed in Table 3.7-7 shall be demonstrated OPERABLE at least once per year by the performance of a loop calibration and operational test.
l McCUIRE - UNITS 1 and 2 3/4 7-44 Amendment No. 93 (Unit 1)
Amendment No. 74 (Unit 2) i
TABLE 3.7-7
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AUXILIARY BUILDING GROUNDWATER LEVEL MONITORS INTERIOR /
LOCATION' EXTERIOR ELEVATION UNIT
-(Feet - Mean Seal Level)
PP51 Interior 731' - 0" 1-i QQ56 Interior 731' - 0" 1 &'2 PP-61 Interior 731' - 0" 2
West Wall Exterior 731' - 0" 1
East Wall.
Exterior 731' - 0" 2
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Amendment No. 74(Unit 2)
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i PLANT SYSTEMS BASES FIRE SUPPRESSION SYSTEMS (Continued)
The Surveillance Requirements provide assurance that the minimum OPERABILITY requirements of the Fire Suppression Systems are met.
An allowance is made for ensuring a sufficient volume of Halon in the Halon storage tanks by verifying either the weight or the level of the tanks.
Level measurements are made by either a U.L. or F.M. approved method.
In the event the Fire Suppression Water System becomes inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant.
3/4.7.11 FIRE BARRIER PENETRATIONS The functional integrity of the penetration fire barriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility.
This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment.
The penetration fire barriers are a passive element in the facility fire protection program and are subject to periodic inspections.
Fire barrier penetrations, including cable penetration barriers, fire doors and dampers are considered functional when the visually observed condition is the same as the as-designed condition.
For those fire barrier penetrations that are not in the as-designed condition, an evaluation shall be performed to show that the modification has not degraded the fire rating of the fire barrier penetration.
During periods of time when a barrier is not functional, either:
(1) a continuous fire watch is required to be maintained in the vicinity of the affected barrier, or (2) the fire detectors on at least one side of the affected barrier must be verified OPERABLE and an hourly fire watch patrol established until the barrier is restored to functional status.
3/4.7.12 AREA TEMPERATURE MONITORING The area temperature limitations ensure that safety-related equipment will not be subjected to temperatures in excess of their environmental qualification temperatures.
Exposure to excessive temperatures may degrade equipment and can cause a loss of its OPERABILITY.
The temperature limits include an allowance for instrument error of 3.9 F.
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McGUIRE - UNITS 1 and 2 B 3/4 7-7 1
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PLANT SYSTEMS l
BASES 3/4.7/13 GROUNDWATER LEVEL Tht:s Technical Specification is provided to ensure that groundwater levels-will be monitored and prevented from rising to the potential failure limit for the McGuire Units I and 2 Auxiliary Buildinos. This notential failure limit is based on engineering calculations that have determined that the Auxiliary Mean Sea Level (ftSL)ptible to overturning due to buoyancy at elevation 737 feet Buildings are susce Under the requirements of this Technical Specification, if groundwater level exceeds elevation 731 feet MSL, (3 out of 5 Tech Spec groundwater monitor alams), and cannot be reduced in one (1) hour, f!cGuire must begin reducing Units 1 and 2 to fiode 5, Cold Shutdown.
This Technical Specification is provided to ensure that groundwater levels will be monitored and prevented from rising to the potential failum limit for the McGuire Units 1 and 2 Auxiliary Buildings. This potential failure limit is based on engineering calculations that have determined that the Auxiliary Buildings are susceptible to overturning due to buoyancy at elevation 737 feet Mean Sea Level (MSL). Under the requirements of this Technical Specification, if groundwater monitor alams), and cannot be reduced in one (1) hour, McGuire must begin reducing Units 1 and 2 to !4ede 5 Cold Shutdown.
Analysis performed by Design Engineering detemined that'the Reactor and t
Diesel Generator Buildings are designed to withstand hydrostatic loadings due to groundwater levels up to elevation 760 feet MSL; therefore, no Technical Specification requirements are specified for these structures.
Elevation 731 feet MSL is the Technical Specification action level of the five Technical Specification groundwater monitors listed in Table 3.7-7.
The East Wall exterior monitor alam at elevation 731 feet MSL is the Alert alarm due to the groundwater well being bored to a depth of 730 feet MSL because of, underground rock fomation below the well. The other four (4) monitors a're Hi-Hi alams at elevation 731 feet (MSL).
The East Wall exterior monitor was originally on the exterior of the Unit 2 Auxiliary Butiding and subsequently was enclosed by the construction of the Equipment Staging Butiding.
As required by Operations procedures, any alams on non-Technical Specifica-tion groundwater monitors will also be investigated. Additionally, if three (3) out of the five (5) Technical Specification Groundwater monitors alam at levels below the Technical Specification action levels, Operations will con-tact Duke Design Engineering (Civil) for investigation and resolution of the increased groundwater level.
If one or more of the 5 Technical Specification groundwater monitors is deter-mined to be inoperable, the monitor (s) will be considered to be indicating above the 731'-0" level until repaired and returned to an operable status.
ficGUIRE - UNITS I and 2 B 3/4 7-8 Amendment No. 93 (Unit 1}
Amendment No. 74 (Unit 2)
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