ML20002C605
| ML20002C605 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/09/1980 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20002C606 | List: |
| References | |
| NUDOCS 8101100557 | |
| Download: ML20002C605 (15) | |
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d' ug#o, UNITED STATES I] e(* * }:
NUCLEAR REGULATORY COMMISSION
. E WASHINGTON, D. C. 20555 PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADEL?HIA ELECTRIC COMPANY DELMARVS DOWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY 00CXET *:0. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 28 License No. DPR-70 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The apolications for amendment by Public Service Electric and Gas Company, Philadelphia Electric Cccoany, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated March 17, August 22, and Sectember 19, 1980, comoly 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 satisfiec.
BID 1100$y
. 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. OPR-70 is hereby amended to read as fallows:
(2) Technical Soecifications The Technical Specifications contair.ad in Appendices A and B, as revised through Amendment No. 28, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license snendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY CO.WISSION
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N.lar C ief Operating Reactqrs Branch #1 DivisionofLicehsing
Attachment:
Changes to the Technical Soecifications Date of Issuance: December 9,1980 L
ATTACHMENT TO LICENSE AMENDMENT NO. 28 FACILITY OPERATING LICENSE NO. DPR-70 00CXET NO. 50-272 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 8-9 3/4 8-9 3/4 8-12 3/4 8-12 3/4 9-10 3/4 9-10 6-3 6-3 6-5 6-5 1
6-15 6-15 6-16 6-16 e
ELECTRICAL POWER SYSTEMS SUAVEILLANCE REOUIREMENTS (Continued) 2.
The oilot cell specific gravity, corrected to 77'F and full electrolyte level, is > l.200.
3.
The pilot cell voltage is 1 2.08 vol ts.
4 The overall battery voltage is 3 125 vol ts.
b.
At least once per 92 days by verifying that:
1.
The voltage of each connected cell is > 2.13 volts under float change and has not decreased more than 0.27 volts from the value observed during the original acceptance test.
2.
The specific gravity, corrected to 77'F and full electrolyte level, of each connected cell is > 1.200 and has not decreased more than 0.02 from the value observed during the previous test.
3.
The electrolyte level of each connected cell is between the minimum and maximum level indication marks.
c.
At least once per 18 months by verifying that:
1.
The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration.
2.
The cell-to-cell and terminal connections are clean, tight, and coated with anti-corrosion material.
3.
The battery charger will supply at least 200 amperes at 125 volts for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
d.
At least once per 18 months, during shutdown, by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the battery is subjected to a battery service test.
e.
At least once per 60 months, during shutdown, by verifying that the battery capacity is at least 80". of the manufacturer's rating when subjected to a per#ormance discharge test. This performance discharge test shall be performed subsecuent to the satisfactory completion of the required battery service test.
l SALEM-UNIT 1 3/4 8-9 AMENDMENT 10. 28
ELECTRICAL POWER SYSTEMS 125-VOLT D.C. DISTRIBUTION - SHUTDCWN LIMITING CONDITION FOR OPERATION 3.8.2.4 As a minimum, the following D. C. electrical equipment and bus shall be energized and OPERABLE:
2 - 125-volt D.C. busses, and 2 - 125-volt batteries, each with at least one full capacity charger, associated with each of the above D.C. busses.
APPLICABILITY: MODES 5 and 6.
ACTION:
With less than the above complement of D.C. equipment and busses OPERABLE, establish CDNTAINMENT INTEGRITY within S hours.
SURVEILLANCE REOUIREMENTS l
l 4.8.2.4.1 The above required 125-volt D.C. busses shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated power availability.
4.8.2.4.2 The above required 125-volt batteries and chargers shall be I
demonstrated OPERABLE per Surveillance Requirement 4.8.2.3.2.
b l
SALEM-UNIT 1 3/4 8-10 i
ELECTRICAL POWER SYSTEMS 28-VOLT D.C. DISTRIBUTION - OPERATING LIMITING CONDITION FOR OPERATION 3.8.2.5 The following D.C. bus trains shall be energized and OPERABLE:
TRAIN 1 A consisting of 28-volt D.C. bus No. l A, 28-volt D.C.
battery No. lA and at least one full capacity charger.
TRAIN 18 consisting of 28-volt 0.C. bus No. 18, 28-volt D.C.
battery No. lB, and at least one full capacity charger.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
a.
With one 28-solt 0.C. bus inoperable, restore the inoperable bus to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be 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 />.
b.
With one 28-volt D.C. battery and/or its charger inoperable, restore the inoperable battery and/or charger to OPERABLf,, status.
within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be 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 />, l
SURVEILLANCE REOUIREMENTS 4.8.2.5.1 Each D.C. bus trai,n shall be detennined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and power availability.
4.8.2.5.2 Each 28-volt battery and above required charger shall be demonstrated OPERABLE:
a.
At least once per 7 days by verifying that:
l.
The electrolyte level tr the pilot cell is between the minimum and maximum level indication marks.
I l
SALEM-UNIT 1 3/4 8-11 1
ELECTRICAL POWER SYSTEMS SURVEILLANCE REOUIREMENTS (Continued) 2.
The pilot cell specific gravity, corrected to 77*F, and full electrolyte 1evel, is > 1.200.
3.
The pilot cell voltage is > 2.08 volts.
4 The overall battery voltage is > 27 volts.
5.
At least once per 92 days by verifying that:
1.
The voltage of each connected cell is > 2.12 volts under float charge and has not decreased more than 0.27 volts from the value observed during the original acceptance test.
2.
The specific gravity, corrected to 77 F and full electro-lyte level, of each connected cell is > 1.200 and has not decreased more than 0.02 from the value observed during the previous test.
3.
The electrolyte level of each connected cell is between the minimum and maximum level indication marks.
c.
At least once per 18 months by verifying that:
1.
The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration.
2.
The cell-to-cell and terminal connections are clean, tight, and coated with anti-corrosion material.
3.
The battery charger will supply at least 150 amperes at 28 volts for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
d.
At least once per 18 months, during shutdown, by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the battery is subjected to a battery service test.
l e.
At least once per 60 months, during shutdown, by verifying that the battery capacity is at least 80". of the manufacturer's rating when subjected to a performance discharge test. This perfonnance discharge test shall be performed subsequent to the satisfactory completion of the required battery service test.
SALEM - UNIT 1 3/4 8-12 AMENDMENT NO. 28
REFUELING OPERATIONS CONTAINMENT PURGE AND PRESSURE-VACUUM RELIEF ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The Containment Purge and Pressure-Vacuum Relief isolation system shall be OPERABLE.
APPLICABILITY: MODE 6.
ACTION:
With the Containment Purge and Pressure-Vacuum Relief isolation system inoperable, close each of the Purge and Pressure-Vacuum Relief penetrations providing direct access from the containment atmosphere to the outside atmosphere. The provision of Specification 3.0.3 are not applicable.
l SURVEILLANCE REGUIREMENTS i
l 4.9.9 The Containment Purge and Pressure-Vacuum Relief isolation system shall be demonstrated OPERABLE within 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to the start of i
and at least once per 7 days during CORE ALTERATIONS by verifying that containment Purge and Pressure-Vacuum Relief isolation occurs on manual initiation and on a high radiation test signal from each of the contain-ment radiation monitoring instrumentation channels.
I SALEM-UNIT 1 3/a 9-9 l
REFUELING OPERATIONS WATER LEVEL - REACTOR VESSEL
- TING CONDITION P3R OPERATION 3.9.10 At least, 23 feet of water shall be maintained over the top of the reactor pressure vessel flange.
APPLICABILITY: During movement of fuel assemblies or control rods within the reactor pressure vessel while in MODE 6.
ACTION:
With the requirements of the above specification not satisfied, suspend all operations involving movement of fuel assemblies or control rods within the pressure vessel. The provicions of Specification 3.0.3 are not a pplicable.
e o
SURVEILLANCE REOUIREMENTS 4.9.10 The water level shall be determined to be at least its minimum required depth within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the start of and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during movements of fuel assemblies or control rods.
SALEM - UNIT 1 3/4 9-10 AMENDMENT NO. 23
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TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION #
LICENSE APPLICABLE MODES CATEGORY 1, 2, 3 & 4 5&6 SOL 1
1*
OL 2
1 Non-Licensed 2
1
- 0oes not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handli..g supervising CORE ALTERATIONS after the initial fuel loading.
- Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on duty shif t crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
SALEM-UNIT l 6-4 m
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ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF 00ALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Padiation Protection Engineer who shall meet or exceed the qualifica-l tions of Regulatory Guide 1.8, September 1975.
6.4 TRAINING
- 6. 4.1 A retraining and replacement training program for the facility staff shall be coordinated by the Assistant to Manager and under the direction of the Training Engineer and shall meet or exceed the require-ments and recommendations of Section 5.5 of ANSI N18.1-1971 and Apoendix "A" of 10 CFR Part 55.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Safety 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 STATION OPERATIONS REVIEW COMMITTEE (SORC)
FUNCTION 6. 5.1.1 The Station Operations Review Committee shall function to advise the Station Manager on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The Station Operations Review Committee shall be composed of
(
the:
l Chainnan :
Chief Engineer Vice Chairman:
Assistant to Manager Member:
Station Operating Engineer Member:
Station Performance Engineer Member:
Reactor Engineer l
l Member:
Senior Shift Supervisor Member:
Senior Performance Supervisor - ISC Member:
Senior Performance Supervisor - Chemistry Member:
Radiation Protection Engineer l
Member:
Senior Maintenance Supervisor Member:
Maintenance Engineer l
l ALTERNATES l
6.5.1.3 All alternate members shall be apoointed in writing by the 50RC Chairman to serve on a temporary basis; however, no more than two alter-i nates snali participate as voting members in 50RC activities at any one time.
SALEM - UNIT 1 5-5 AMEN 0 MENT NO. J3, 77, 73, 25, 28
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ADMINISTRATIVE CONTROLS MEETING FRECUENCY 6.5.1.4 The 50RC shall meet at least once per calendar month and as convened by the 50RC Chairman or his designated alternate.
OUORUM 6.5.1.5 A quorum of the 50RC shall consist of the Chairman or his designated alternate and four members including alternates.
RESPONSIBILITIES 6.5.1.6 The Station Operations Review Committee shall be responsible for:
a.
Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by the Station Manager to affect nuclear
- safety, b.
Review of all proposed tests and experiments that affect nuclear safety.
c.
Review of all proposed changes to Appendix "A" Technical Specifications.
d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety, e.
Investigation of all violations of the Technical Specifications l
including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the General Manager - Electric Production and to the Chairman of the Nuclear Review Boar'd.
f.
Review of events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission.
g.
' Review of facility operations to detect potential nuclear safety hazards.
h.
Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Nuclear Review Board.
SALEM-UNIT 1 6-6 l
ADMINISTRATIVE CONTROLS c.
Records of facility radiation and contamination surveys.
d.
Records of radiation exposure for all individuals entering radiation control areas, e.
Records of gaseous and liquid radioactive material released to the environs, f.
Records of transient or operational cycles for those facility components identifled in Tabl e 5.7-1.
g.
Records of training and qualification for current memebers of the plant staff.
h.
Records of in-service inspections performed pursuant to these Technical Specifications,
- i. Records of Quality Assurance activities required by the QA Manual.
J.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the 50RC and the NRB.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by issuance of a Radiation Exposure Permit *. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
"Raciation Protection personnel or personnel escorted by Radiation Protection personnel shall be exempt from the REP issuance requirement during the performance of their assigned radiation protection duties, provided they comoly with approved radiation protection procedures for entry ir.to high radiation areas.
SALEM - UNIT 1 5-15 AMENCMENT NO. 79, 23
ADMINISTRATIVE CONTROLS a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates *.he radiation dose rate in the area and alarms when a preset inte-grated dose is received. Entry into such areas with this moni-toring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them.
c.
An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Senior Supervisor - Radiation Protection in the Radiation Exposure Permit.
6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr. In addition, locked doors shall be provided to prevent unauth-orized entry into such areas and the keys shall be maintained under the administrative control of the Senior Shift Supervisor on duty and/or the Senior Supervisor - Radiation Protection.
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l SALEM - UNIT 1 6-16 AMENDMENT NO. 28 I
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