ML20248C998
| ML20248C998 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 09/22/1989 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20248D003 | List: |
| References | |
| NUDOCS 8910040091 | |
| Download: ML20248C998 (6) | |
Text
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jo UNITED STATES '
NUCLEAR REGULATORY COMMISSION o
^L E'
WASHINGTON, D. C. 20555
...../
THE CLEVELAND ELECTRIC ILLUMINATING COMPANY, ET AL.
DOCKET NO. 50-440 PERRY NUCLEAR POWER PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 25 License No. NPF-58 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by The Cleveland Electric Illuminating Company, Duquesne Light Company, Ohio Edison Company,(Pennsylvania Power' Company, and Toledo Edison Company the licensees) dated August 23, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, 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; 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.
2.
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 Facility Operating License No.
NPF-58 is hereby amended to read as follows:
8910040091 890922 fM ADOCK 05o0044o PDC
,, (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environ-mental Protection Plan contained in Appendix B, as revised through Amendment No. 25 are hereby incorporated into this license. The Cleveland Electric Illuminating Company 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 John N. Hannon, Director Project Directorate III-3 Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 22, 1989
ATTACHMENT TO LICENSE AMENDMENT NO. 25 FACILITY OPERATING LICENSE NO. NPF-58 DOCKET NO. 50-440 Replace the following aages of the Appendix "A" Technical Specifications with the attached pages. T1e revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Overleaf pages are provided to maintain document completeness.
Remove Insert 3/4 3-82 3/4 3-82 B 3/4 3-5
.B 3/4 3-5 L
INSTRUMENTATION SOURCE RANGE MONITORS LINITING CONDITION FOR OPERATION 3.3.7.6 At least the' following source range monitor channels shall be OPERABLE:
a.
In OPERATIONAL CONDITION 2*, three.
b.
In OPERATIONAL CONDITION 3 and 4, two.
APPLICABILITY: OPERATIONAL CONDITIONS 2*, 3 and 4.
ACTION:
a.
In OPERATIONAL CONDITION 2* with one of the above required source range monitor channels inoperable, restore at least 3 source range monitor channels to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUT 00WN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
In OPERATIONAL CONDITION 3 or 4 with one or more of the above required source ange monitor channels inoperable, verify all insertable con-trol u es to be fully inserted in the core and lock the reactor mode switch in the Shutdown position within one hour.
SURVEILLANCE REQUIREMENTS 4.3.7.6 Each of the above required source range monitor channels shall be demonstrated OPERABLE by:
a.
Performance of a:
1.
CHANNEL CHECK at least once per:
a) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in CONDITION 2*, and b) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in CONDITION 3 or 4.
2.
CHANNEL CALIBRATION ** at least once per 18 months.
b.
Performance of a CHANNEL FUNCTIONAL TEST:
1.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to moving the reactor mode switch from the Shutdown position, if not performed within the previous 7 days, and 2.
At least once per 31 days.
c.
Verifying, prior to withdrawal of control rods, that the SRM count rate is at least 0.7 cps *** with the detector fully inserted.
- With IRM's on range 2 or below.
- Neutron detectors may be excluded from CHANNEL CALIBRATION.
- Provided the signal-to-noise ratio is > 2.
PERRY - UNIT 1 3/4 3-81
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INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 3/4.3.7.4 REMOTE SHUTDOWN INSTRUMENTATION AND CONTROLS The OPERABILITY of the remote shutdown monitoring instrumentation and controls ensures that sufficient capability is available to permit shutdown and maintenance of HOT SHUTDOWN of the unit from locations outside of the control room. This capability.is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
3/4.3.7.5 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that suffi-cient information is available on selected plant parameters to monitor and assess important variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident,"
December 1975 and NUREG-0737, " Clarification of TMI Action Plan Requirements,"
November 1980. The CHANNEL CHECK for the Primary Containment Isolation Valve'
. Position consists of the verification that indication of valve position (open or closed) can be determined by the valve position lights in the control room. The CHANNEL CALIBRATION for the Primary Containment Isolation Valve Position consists of the Position Indicator Test (PIT), which is conducted in accordance with Specification 4.0.5.
3/4.3.7.6 SOURCE RANGE MONITORS The source range monitors provide the operator with information of the status of the neutron level in the core at very low power levels during startup and shut-down. At these power levels, reactivity additions shall not be made without this flux level information available to the operator. When the intermediate range monitors are on scale, adequate information is available without the SRMs and they can be retracted.
The SP,Ms are required OPERABLE in OPERATIONAL CONDITION 2 to provide for rod block capability, and are required OPERABLE in OPERABLE CONDITIONS 3 and 4 to provide monitoring capability which provides diversity of protection to the mode switch interlocks.
3/4.3.7.7 TRAVERSING IN-CORE PROBE SYSTEM The OPERABILITY of the traversing in-core probe system with the specified
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minimum complement of equipment ensures that the measurements obtained from use of this equipment accurately represent the spatial gama flux distribution of the reactor core. With less than the specified complement of equipment, the spatial gama flux distribution of the reactor core can still be accurately represented by using replacement data from symetrical strings (LPRM locations), provided the conditions specified in the LC0 are met.
The TIP system OPERABILITY is demonstrated by normalizing all probes (i.e..
detectors) prior to performing an LPRM calibration function. Monitoring core thermal limits may involve utilizing individual detectors to monitor selected areas of the reactor core, thus all detectors may not be required to OPERABLE. The OPERABILITY of individual detectors to be used for monitoring is demonstrated by comparing the detector (s) output with data obtained during the previous LPRM calibrations.
PERRY - UNIT 1 B 3/4 3-5 Amendment No. 25
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I INSTRUMENTATION BASES
-MONITORING INSTRUMENTATION (Continued) 3/4.3.7.8 LOOSE-PART DETECTION SYSTEM The OPERABILITY of the loose part detection ~ system ensures that sufficient capability is available to detect loose metallic parts in the primary system and avoid or mitigate. damage to primary system components.. The allowable out-of-service times and surveillance requirements are consistent with the recommen-dations of Regulatory Guide 1.133 " Loose Part Detection Program for the Primary System of Light-Water-Cooled Reactors," May 1981.
3/4.3.7.9 RADIOACTIVE LIQUID EFFLUENT MDNITORING INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.
The alare/
trip setpoints for.these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alare/ trip will occur prior to exceeding the limits of 10 CFR Part 20.
The OPERABILITY and use of this instru-mentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
3/4.3.7.10 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.
The alarm setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM to ensure that the alarm will occur prior to exceeding the limits of 10 CFR Part 20.
This instrumentation also includes provisions for' monitoring the concentrations of potentially explosive gas mixtures in the GASEOUS RADWASTE TREATMENT SYSTEM.
The OPERABILITY and use of this instrumen-tation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM This specification is provided to ensure that the turbine overspeed protection system instrumentation and the turbine speed control valves are d
OPERABLE and will protect the turbine from excessive overspeed.
Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety related components, equipment or structures.
3/4.3.9 PLANT SYSTEMS ACTUATION INSTRUMENTATION The plant systems actuation instrumentation is provided to initiate action of the containment spray system in the event of a LOCA witn high containment PERRY.- UNIT 1 8 3/4 3-6
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