ML15113A147

Amends 133,133 & 130 to Licenses DPR-38,DPR-47 & DPR-55, Respectively,Revising Tech Specs to Reflect Current Regulations Governing LERs Required by Commission

ML15113A147
Person / Time
Site:	Oconee
Issue date:	01/09/1985
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Duke Power Co
Shared Package
ML15113A148	List: ML15113A147 ML15113A149
References
DPR-38-A-133, DPR-47-A-133, DPR-55-A-130 NUDOCS 8502250786
Download: ML15113A147 (15)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 133 License No. DPR-38

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Duke Power Company (the licensee) dated April 30, 1984, 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 Specifications as indicated in the attachment to this ltcense

.amendment, and paragraph 3.8 of Facility Operating License No. DPR-38 is hereby amended to read as follows:

3.8 Technical Specifications The Technical Specifications contained in Appendices A and B,.as revised through Amendment.No.133 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

8502250786 850109 PDR ADOCK 05000269 p

PDR

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3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Jo n F. Stolz, Chief O erating Reactors Br ch #4 ivision of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: January 9, 1985

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

133 License No. DPR-47

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Duke Power Company (the licensee) dated April 30, 1984, 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 Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-47 is hereby amended to read as follows:

3.B Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.133 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

%Jo n F. Stolz, Chief rating Reactors anch #4 Division of Licensing Changes to the Technical Specifications Date of Issuance: January 9, 1985

• NITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

130 License No. DPR-55

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Duke Power Company (the licensee) dated April 30, 1984, 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:amendedby changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. 5PR-55 is hereby amended to read as fo1lows:

3.B Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.130 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION oh F. Stolz, Chie rating Reactors Branch #4 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: January 9, 1985

ATTACHMENTS TO LICENSE AMENDMENTS AMENDMENT NO. 133 TO DPR-38 AMENDMENT NO. 133 TO DPR-47 AMENDMENT NO. 130 TO DPR-55 0OCKETS NOS. 50-269, 50-270 AND 50-287 Replace the following pages of the Appendix "A" Technical Specifications with the attaChed pages. The revised pages are identified by amendment numbers and contain vertical lines indicating the area of change.

Remove Pages Insert Pages v-a v-a 3.17-1 3.17-1 3.17-2 3.17-2 3.17-3 3.17-3 6.2-1 6.2-1 6.5-1 6.5-1 6.6-4 6.6-4 6.6-5 6.6-5 6.6-6 6.6-6a 6.6-7

Section Paze 6.5 STATION OPERATING RECORDS 6.5-1 6.6 STATION REPORTING REQUIREMENTS 6.6-1 6.6.1 Routine Revorts 6.6-1 6.6.2 Non-Routine Resorts 6.6-4 6.6.3 Soecial Reoorts 6.6-5 6.7 ENVIRONMENTAL QUALIFICATION 6.7-1 6.8 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.8-1 Amendments Nos. 133 133, & 130 v-a

3.17 FIRE PROTECTION AND DETECTION SYSTEMS Applicability This specification applies to the operability of fire protection and detection systems when equipment protected by those systems is required to be operable.

Objective To assure the operability of fire protection and detection systems which pro tect systems and equipment required for safe shutdown.

Specification 3.17.1 The minimum fire detection instrumentation for each fire detection zone shown in Table 3.17-1 shall be operable. The fire detection instruments located within the containment are not required to be operable duringthe performance of Type A Containment Leakage Rate Tests. When this specification is determined not to be met, appropria te action shall be taken consisting of one or more of the following:,

1. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, a fire watch patrol shall be established to in spect an accessible zone with the inoperable instrumentation at least once per hour.

2. The inoperable instrumentation shall be restored to operable status within 14 days or a report shall be submitted to the Commission within the next 30 days outlining the action taken, the cause of the inoperability and.the plans and schedule for restoring the instrumentation to operable status. Continued operation of' the affected unit is permitted provided that this condition is met. Operation under this specification is not considered to be in a degraded mode and thus is not reportable under Technical Specification 6.6.2.1.

3.17.2 The Fire Suppression Water System shall be operable. This system shall consist :of 2 High Pressure Service Water (HPSW) pumps with a design capacityof 6000.gpm each and automatic initiation logic.,

and the associated piping and valves supplying water to the sprinkler systems and fire hose stations. -The HPSW pumps shall be aligned to the high-pressure fire header. When this specification is determined not to be met, appropriate action shall be taken con sisting of the following:

1. The inoperable equipment shall be restored to operable sta tus within 7 days: or a report shall be submitted to the Commis sion within the next 30 days outlining the plans and procedures to be used to provide for the loss of redundancy in this system.

Continued operation of the affected unit is permitted provided that this condition is met. Operation under this specification is not considered to be in a degraded mode and thus is not reportable under Technical Specification 6.6.2.1.

Amendments Nos.

133,133

, &130 3.17-1

2. With no Fire SuppressioniWateraSystem operable, in lieu-of the above, the following action shall be taken.

a. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a backup Fire Suppression Water System shall be established.

If a backup Fire Suppression Water System cannot be established within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, place the reactor in Hot Standby within the next twelve (12) hours and in cold shutdown within the following forty-eight (48) hours.

b. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the Commission shall be notified by tele phone, and in writing no later than the first working day following the event.

C. Within 14 days of the event, a report shall be submitted to the Commission outlining the action taken, the' cause of the inoperability and the plans and schedule for restoring the system to operable status.

3.17.3 The sprinkler and spray systems in safety related areas listed in Tabler3.17-1 shall be operable. If a system is determined to be inoperable, the following corrective action shall be taken.

1. A continuous fire watch with backup fire suppression equipment shall be established in the area within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.. The sprinkler or spray system shall be restored to operable status within 14 days or a report-shall be submitted to the Commission within-the next 30 days outlining the cause o-f in-*

operability and the plans for restoring the system to operable status.

Continued operation of the affected unit is permitted provided that this condition is met. Operation under this speci fication is not considered to be a degraded mode and thus is not reportable under Technical Specification 6.6.2.1..

3.17.4 The automatic CO2 system provided for the generators at the Keowee Hydro Station sha-lbe.. operable. If the system is determined to be inoperable the following corrective action shall. be takene:

1. A continuous fire watch with batkup,fire suppression equipment shall be established in the area within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2. The CO, system'shall be :restored to operable status with in 14 days or a report shall be submitted to the Commission within the next 30 days outlining the cause of inoperability and the plans for restoring the system to operable status. Con tinued operation of the affected reactor unit is permitted o

provided that this condition is met. Operation under this speci fication is not considered to be in a degraded mode and thus is not reportable under Technical specification 6.6.2.1.

Amendments Nos. 133,

133, & 130 3.17-2

3.17.5 The fire hose stations listed in Table 3.17-1 shall be operable or the following action shall be taken:

1. If a fire hose station listed in Table 3.17.1 is inoperable, an additional equivalent capacity fire hose of length sufficient to reach the unprotected area shall be provided at an operable hose station within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2. If the inoperable fire hose station cannot be restored to operable status within 14 days, continued operation of the affected unit is permitted provided that within the next 30 days a report is submitted to the Commission outlining the cause of the inoperability, actions taken, and the plans for restoring the system to operable status.

Operation under this specifica tion is not considered to be a degraded mode and is not report able under Tech. Spec. 6.6.2.1.

3.17.6 All.fire barrier penetrations (including cable penetration barriers, fire doors, fire-dampers) protecting safety related areas shall be operable.

If a fire barrier protecting a safety-related area is determined to be inoperable, the operability status of the fire detection instru mentation for the affected safety related area(s) shall be determined within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and the following action shall be taken:

1. If the fire detection instrumentation for the affected area(s) is operableea fire watch patrol shall be established to inspect the area-at least once per hour,.

2. If the fire detection instrumentation-is inoperable, a contin uous fire watch shall be established within the next hour on at least one side of the affected penetration fire barrier. The non-functional fire barrier penetration(s) shall be restored to functional status within 7 days.

3.

If the non-functional fire barrier penetration(s) cannot be re stored to functional status within 7 days, continued operation of the affected unit is permitted provided -that-within the-next

.30 days, a report is submitted to the Commission outlining the cause of the inoperability and the plans for-restoring the esys tem to operable status. Operation under this specification is not considered to be a degraded mode and -is not reportable under Technical Specification 6.6.2.1.

Bases Operability of the fire detection instrumentation ensures that adequate.warning capability is available for the prompt detection of fires. This capability is required in order to detect and locate fires in their early stages.

Prompt detection of fires will reduce the potential for-damage to safety related equip ment and is an integral element in the overall facility fire protection program.

Amendments Nos. 133

, 133

, & 130 3.17-3

6.2 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE EVENT 6.2.1 Any reportable event shall be investigated promptly by the station Manager.

6.2.2 The Vice President, Nuclear Production Department shall be notified of any reportable event..

A written report shall be prepared which describes the circumstances leading up to and resulting from the incident and shall recommend appropriate action to prevent or minimize the probability of a recurrence. The report shall be submitted to the Vice President, Nuclear Production Department, and the Director of the Nuclear Safety Review Board.

6.2.3 The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.6.2.

Amendments Nos. 133 -133

, &130 6.2-1

6.5 STATION OPERATING RECORDS Specification 6.5.1 The following records shall be prepared and permanently retained in a manner convenient for review:

a.. Records of modifications to the station as described in the FSAR.

b. Special nuclear material physical inventory records.

c. Special nuclear material isotopic inventory records.

d. Radiation monitoring records, including records of radiation and contamination surveys.

e. Records of off-site environmental surveys.

f. Personnel radiation exposure records as required by 10CFR20.

g. Records of radioactive releases and waste disposal.

h. Records of reactor coolant system in-service inspections.

i. Preoperational testing records.

j. Records of special reactor tests or experiments.

k. Records of changes to safety-related operating procedures.

1. Records for Environmental Qualification which are covered under the provisions of paragraph 6.7.

m. Records of the seal service-lives of hydraulic snubbers.

6.5.2 The following records shall be prepared and retained for a minimum of six (6) years in a manner convenient for review:

a. Switchboard Record.

b. Reactor Operations Logbook.

c.

Shift Supervisor Logbook.

d. Maintenance histbries for station safety-related structures, systems and components.

e. Records of safety-related inspections, other than reactor coolant system in-service inspections..

f. Records of reportable events.

g. Periodic testing records and records of other periodic checks, calibrations, etc. performed in accordance with surveillance requirements for safety-related parameters, structures, systems and components.

Amendments Nos. 133

, 133

, & 130 6.5-1

6.6.2 Non-Routine Reports 6.6.2.1 Reportable Events Reporting requirements for Licensee Event Reports are contained in 10 CFR 50, §50.73.

6.6.2.2 Environmental Monitoring

a. If individual milk samples show 1-131 concentrations of 10 picocuries per liter or greater, a plan shall be submitted within one week advising the NRC of the proposed action to ensure the plant related annual doses will be within the design objective of 45 mrem/yr to the thyroid of any individual.

b. If milk samples collected over a calendar quarter show average concen trations of 4.8 picocuries.per liter or greater,. a plan shall be sub mitted within 30 days advising the NRC of the proposed action to ensure the plant related annual doses will be within the design objective of 45 mrem/yr to the thyroid of any individual.

Amendments Nos.

133,133

, &130 6.6-4.

6.6.3 Special Revorts Special reports shall be submitted to the Regional Administrator, Region II, within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of'the applicable reference specification:

a.

Single Loop Restrictions, Specification 3.1.8.

b.

Auxiliary Electrical Systems-, Specification 3.7

c. Radioactive Liquid Effluents, Dose, Specification 3.9.2 Liquid Waste Treatment, Specification 3.9.3 Chemical Treatment Ponds, Specification 3.9.4

d.

Radioactive Gaseous Effluents, Dose, Specification 3.10.2 Gaseous Radwaste Treatment, Specification 3.10.3

e.

Fire Protection and Detection Systems, Specification 3.17

f. Reactor Coolant System Surveillance, Inservice Inspection, Specification 4.2.1 Reactor Vessel Specimen, Specification 4.2.4

g.

Reactor Building Surveillance, Coatainment.Leakage.Tests,.Specification 4.4.1

h.

Structural Integrity Surveillance, Tendon Surveillance, Specification 4.4.2.2

i.

Radiological Environmental Monitoring Program, Specification 4.11.1 Land Use Census, Specification 4.11.2

j.

Dose Calculations (40 CFR 190), Specification 4.21 Amendments NOs. 133

, 133

& 130 6.6-5