ML17053C570
| ML17053C570 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/13/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17053C571 | List: |
| References | |
| NUDOCS 8105010523 | |
| Download: ML17053C570 (24) | |
Text
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e UNITEO STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 NIAGARA MOHAWK POWER CORPORATION DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 42 License No.
DPR-63 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment hy Niagara Mohawk Power Corporation (the licensee) dated September 17, 1980;;:complies with the standards and requirements 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 conformity with the application, 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; 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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.
DPR-63 is hereby amended to read as follows:
(2) Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 42
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Speci'fications-.
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This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
APril 13, 1981 Thomas
. Ippolito, Chief Operating Reactors Branch P2 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NO. 42 FACILITY OPERATING LICENSE NO.
DPR-63 DOCKET NO. 50-220 Revise Appendix A as follows:
Remove 249 )
~264 J f 265
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Insert ilia v
241ee 241 ff 24lgg 241hh 241ii (264.
249
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SECTION DESCRIPTION PAGE 3.6.5 Radioactive Material Sources 4.6.5 Radioactive Material Sources 241k 3.6.6 Fire Detection 4.6.6 Fire Detection 241m 3.6.7 Fire Suppression 3.6.8 Carbon Dioxide Suppression System 3.6.9 Fire Hose Stations 3.6.10 Fire Barrier Penetration Fire Seals 4.6.7 4.6.8 4.6.9 Fire Suppression Carbon Dioxide Suppression System Fire Hose Stations 241q 241u 241y 4.6.10 Fire Barrier Penetration Fire Seals 24lcc 4.6.11 Accident Monitoring Instrumentation 241ee Amendment No.
42
SECTION DESCRIPTION PAGE 6.11 6.12 6.. 13 6.14 6. 1-5 L6. 16 Radiation Protection Program Respiratory Protection Program High Radiation Area Fire Protection Inspection
- Environmental Qualification Systems Int'hgrity 260 260 263
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- 6. 17 Iodine Monitoring 264 Amendment No.
42
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LIHITING CONDITIOiN FOR OPERATION SURVEILLANCE REQUIREHENT 3.6. 11 ACCIDENT HONITORING INSTRUkiENTATIOiV 4.6.11 ACCIDENT HONITORXNG INSTRUHENTATION Applies to the operability of the plant instrumentation that performs an accident monitoring function.
Applies to the surveillance of the instrumentation that performs an accident monitoring function.
~Ob'e=tive:
To assure high reliability of the accident monitoring instrumentation.
~Ob'ective:
To verify the operability of accident monitoring instrumentation.
a.
During the power operating condition, the accident monitoring instrumentation sensors shown in Table 3.6.11 shall be operable except as specified in 3.6.11 b or c.
Instrument channels shall be tested and calibrated at least as frequently as listed in Table 4.6.11.
b.
Safet and Relief Valves (1) With the number of operable accident monitoring instrumentation sensors (for parameters 1 and 2) 1 less than the num5er shown in Table 3.6.11 restore to an operable status during the next cold shutdown when there is access to the drywell.
(2) With the number of operable accident monitoring instrumentation sensors (for parameters 1 and 2) 2 less than the num5er shown in Table 3.6.11 restore an inoperable sensor to an operable status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(3) The total number of sensors shown in Table 3.6.11 will be operable prior to the beginning of each cycle.
241ee Amendment No.
42
LIHITING CONDITION FOR OPERATION SURVEILLANCE REQUIREHENT 3.6.11 ACCIDENT HONITORING INSTRUHENTATION (continued) c.
Reactor Vessel Water Level (1) With the number of operable accident monitoring instrumentatin sensors less than the total number of sensors (for parameter
- 3) shown in Table 3.6.11, either r'estore the inoperable sensor(s) to operable status within 7'ays, or be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(2) With the number of operable accident monitoring instrumentation sensors (for parameter
- 3) less than the minimum number of operable sensors of Table 3.6.11, either restore the inoperable sensor(s) to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Amendment No.
42 241ff
Table 3.6.11 Accident Monitorin Xnstrumentation Parame ter Total Number of Sensors Minimum Number-of 0 erable Sensors (1)
Relief valve position indicator
.-'2~/va 1 c e
.1/valve E
(2)
Safety valve position indicator Z'/valve 1/valve (3)
Reactor vessel water level 241 SS Amendment No.
42
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Table 4.6.ll Accident Honitorin Instrumentation Surveillance Re uirement Parameter Instrument Channel Test Instrument Channel Calibration (1) Relief valve position indicator (Primary Acoustic)
Once per month Once during each major refueling ou Relief valve position indicator (Backup Thermocouple) )
Once per month Once during each major refueling outage (2)
Safety valve position indicator (Primary Acoustic)
Once per month Once during each major refueling outage Safety valve position indicator (Backup Thermocouple)
Once per month Once during each major refueling outage (3)
Reactor vessel water level Once per month Once during each major refueling outage 24lhh Amendment No.
42
Bases 3.6.11 and 4.6.11 Accident Honitorin~ Instrumentation Accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables during and following an accident.
This capability is consistent with the recommendations of NUREG-0578, "THI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."
241 ii Amendment No.
42
6.3 Facilit Staff Qualifications 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Snift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
6.4 Training 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975 except for Fire Brigade Training sessions which shall be held at least quarterly.
6.5 Review and Audit 6.5.1 Site 0 erations Review Committee (SORC)
Function 6.5.1.1 The Site Operations Review Committee shall function to advise the General Superintendent Nuclear Generation on all matters related to nuclear safety.
Composition 6.5.1.2 The Site Operations Review Committee shall be composed of the:
Chairman:
Member:
Member:
Member:
Member.'ember.
Member:
General Superintendent Nuclear Generation Station Superintendent Nuclear Generation Superintendent Results Nuclear Supervisor Reactor Analysis Superintendent Maintenance Nuclear Supervisor Instrument
& Control Nuclear Supervisor Radiochemical
& Radiation Protection 249 Amendment No.
42
6.14 Fir.e Protection Ins ection 6.14.1 An independent f]re protection and loss prevention inspection and audit shall be performed annually utilizing either qual)fied off-s3te licensee personnel or an outside fire protection firm.
6.14.2 An inspection and audit by an outside qualified fire consultant shall be performed at intervals no greater than 3 years.
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6.15 Environmental uglification h.
Dy no later than June 30, 1902 all safety<<related electrical equipment fn the facility shall be qualified ir> accordance with the Provisions of. Division of Operating Reactors "Guidelines for Evaluating Environmental qualification o'f Class IE Electrical Equipment
$ n Operating Reactors" (DOR Guidelines); or; NUREG-0588 "Interim Staff Position on Environmental qualification of Safety-Related Electrical. Equipment".,
December 1979.
Copies of )hose documents are attached to Order for Modification of License DPR<3..dated October 24, 1980.
B.
Dy no later than Oecember 1, 1900, complete and auditible records must be available and maintained at a central location which describe tho env)ronmental qualification method used for all safoty-related electrical equipment
$ n sufficient data)1 to document tire degree of complianco w$ tli the.
DOR Guidolines or NUREQ-0500.
Thereafter, such records should bo updated and ma$ nta$ nod current as equipment is replaced, further tosted, or othorwiso furthor qualified.
6.16 S stems Inte rit Procedure shall be established, implemented
'and maintained to meet or exceed the requirements and recommendations of section 2.1.6.a of NUREG 0578.
4 6.17 Iodine Monitorin Procedures shall be established, implemented and maintained" to meet or exceed the requirements and recommendations of section 2.1;8.c of NURfG 0578.
Amendment No. g8, 42 0< m H.EI 264