ML19250C241
| ML19250C241 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/07/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19250C239 | List: |
| References | |
| NUDOCS 7911230079 | |
| Download: ML19250C241 (21) | |
Text
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[pa arc j UNITED STATES uy g
NUCLEAR REGULATORY COMMISSION y
g WASHINGTON, D. C. 20555 3
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FLORIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNE1.L CITY OF GAINESVILLE CITY OF KISSIMMEE CITY OF LEESBURG CITY OF NEW SMYRNA BEACH AND UTILITIES COMMISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMMISSION AND CITY OF ORLANDO SEBRING UTILITIES COMMISSION SEMIN0LE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.25 License No. DPR-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Florida Power Corporation, et al (the licensees) dated July 21, 1977, September 22, 1978, and May 23, 1979 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regu-lations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the applications, 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.
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~ 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. DPR-72 is hereby amended to read as follows: '(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 25, are hereby incorporated in the license. Florida Power Corporation shall operate the facility in accordance with the Technical Specifications. 3. This license amendment is effective as of the date of its issuance. FOR THE NUCLEAR REGULATORY COMMISSION b. y Robe ~t W. Reid, Chief Operating Reactors Branch =4 Division of Operating Reactors
Attachment:
Changes to the Technical e Specifications Date of Issuance: November 7, 1979 13"6 119
ATTACHMENT TO LICENSE AMENDMENT NO. 25 FACILITY OPERATING LICENSE N0. DPR-72 DOCKET N0. 50-302 Replace the following pages of the Appendices "A" and "B" Technical Speci-fications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness. Appendix A Pages Appendix B Pages 6-2 5-1 6-6 5-2 6-7 5-4 6-11 5-4a (new page) 6-12 5-4b (new page) 6-16 5-5 5-6 1306 120
s 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Nuclear Plant Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence. 6.1.2 The Nuclear Plant Manager shall be responsible for an annual fire protection inspection which shall be performed utilizing either qualified offsite licensee personnel or an outside fire protection firm. The inspection shall consist of: a) an inspection of safety-related areas of the Plant to verify that they are in conformance with the fire hazards analysis; and b) a review of the Fire Brigade organization, training, and drills to verify their conformance with the requirements of Section 27 of the NFPA Code-1976. 6.1.3 The Nuclear Plant Manager shall be responsible for an inspection of the fire protection program to be performed by a qualified outside fire consultant at least once per 36 months. 6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2-1. FACILITY STAFF 6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and: a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1. b. At least one licensed Operator shall be in 'the control room when fuel is in the reactor. c. At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and during recovery frcm reactor trips. d. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor. e. All CORE ALTERATIONS after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operatica. ~ f. A Fire Brigade of at least 4 members shall be naintained onsite at all times. This excludes 5 members of the minimLa snitt crew necessary for safe shutdown of the plant and personnel required for other essential functions. NCRYSTALRIVER-UNIT 3 6-1 Amendment No. 4, 13 iP6 121
nW (A PRESIDENT -4 [." F LORIDA POWER CORP.
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h SE NIOR SElsl0R VICE PRES 40ENI VICE PRESIDE NT y COHPOR AIE SE RVICES E NGINE E RIN G 8 & GEN COUNSEL &CONSTRUCil04 NUCL E AR GENERAL C 3r REVIEW COMM (NCRC) ASST. VICE PRE 5. POWER ( PR00UC T10M A f STRAilVE POWER PRODUCTION SERVICES VICE PRESIDENT ENVIHONMENT M AN AGE R MANAGER MANAGER MANAGER O &NEW F OSSIL GAS TUR88NE PRODutil0N NUCLE AR k TECHNOLOGY OPE R All0NS OPE R Ail 0NS ENGINE ERINr OPE R Ail 0NS NUCLE AR DIRECIOR DIRE CT OR DIRECTOR PLANT DIRECTOR E NVIR0!: MENTAL & FUEt & SPECIAL PU RCH ASING & MANAGER UUAtifYPROGHAp*5 LICENSING AF F AIRS PROJEti$ STORES OU AttiY PROGR AMS ENVIRONMENTAL & REG. FUELS MANAGER M AN AGE R "#"#0IN PR000Cil0N Ilu CL E AR PR00UCil04 MAINT E N ANCE $UPPORT SERVICES QUAlliY MANAGER SE RVICE S SERVICES h PROGRAM POWERP1 ANT
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SUPE RVISO P. QUAllTY & 011 All1Y Q U AllTY REllABILITY PROGRAM PROGRAMS y ENGINEERING AUDITS tha STAFF STAFF STAFF N, CC N t.rl Fquie 6.2-1 Of fule Organaalma n e .~..~ey.-~~
ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimu:n qualifications of ANSI N18.1-1971 for comparable positions, except for the Chemistry and Radiation Protection Engineer who shall meet or exceed i the qualifications 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 maintained under the direction of the Nuclear Plant Manager I and shall meet or exceed the requirements and reconmendations 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 Nuclear Plant Manager and shall meet or exceed the requirements of Section 27 of the NFPA Code-1976, except for Fire Brigade training sessions which shall be held at least quarterly. 6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW COMMITTEE (PRC) FUNCTION 6.5.1.1 The Plant Review Committee shall function tn c.dvise the Nuclear Plant Manager on all matters related to nuclear safety. COMPOSITION 6.5.1.2 The Plant Review Coninittee shall be composed of the: Chairman: Technical Services Superintqndent Member: Operations Superintendent Member: Technical Support Engineer Member: Maintenance Superintendent Member: Chemistry and Radiation Protection Engineer Member: At large (Designated by Chairman) ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PRC Chairman to serve on a temporary basis; no more than two alternates shall participate as voting members in PRC activities at any one time. ~ MEETING FREQUENCY 6.5.1.4 The PRC shall meet at least once per calendar month and as convened by the PRC Chairman or his designated alternate. CRYSTAL RIVER - UNIT 3 6-5 Amendment No. 5, }d 14
s ADMINISTRATIVE CONTROLS QUORUM 6.5.1.5 A quorum of the PRC shall consist of the Chairman or his designated alternate and four members including alternates. RESPONSIBILITIES 6.5.1.6 The Plant Review Comittee shall be responsbile 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 Nuclear Plant Manager to affect nuclear safety. b. Review of all proposed tests and experiments that affect nuclear Safety, c. Review )f all proposed changes to the Appendix "A" Technical Specif. cations. 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 including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Manager, Nuclear Operations and to the Chairman of the Nuclear General Review Committee. f. Review of events requiring 24 hour 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 General Review Committee. i. Review of the Plant Security Plan and implerrenting procedures and shall submit recommended changes to the Chairman of the Nuclear General Review Committee. j. Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairman of the Nuclear General Review Comittee. CRYSTAL RIVER - UNIT 3 6-6 Amendment No. E,2 5 1306 124
r ADMINISTRATIVE CONTROLS AUTHORITY 6.5.1.7 The Plant Review Committee shall: a. Recommend to the Nuclear Plant Manager written approval or disapproval of items considered under 6.5.l(a) through (d) above. b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above con-stitutes an unreviewed safety question. c. Provide written notification within 24 hours.to the Manager, Nuclear Operations and the Nuclear General Review Committee of disagreement between the PRC and the Nuclear Plant Manager; however, the Nuclear Plant Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above. RECORDS 6.5.1.8 The Plant Review Connittee shall maintain written minutes of each meeting and copies shall be provided to the Manager, Nuclear Operations and Chairman of the Nuclear General Review Committee. 6.5.2 NUCLEAR GENERAL REVIEW COMMITTEE (NGRC) FUNCTION 6.5.2.1 The Nuclear General Review Committee shall function to provide independent review and audit of designated activities in the areas of: a. Nuclear power plant operations b. Nuclear engineering c. Chemistry and radiochemistry d. Metallurgy e. Instrumentation and control f. Radiological safety g. Mechanical and electrical engineering h. Quality assurance practices
- ,YSTAL RIVER - UNIT 3 6-7 Amendment No. 5,25 13 R6
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ADMINISTRATIVE CONTROLS COMPOSITION, 6.5.2.2 The NGRC shall be composed of the Chairman, Vice Chairman, and at least 5 members. No more than a minority of the members shall have line responsibility for operation of the facility. The committee shall collec-tively have the experience and competence required to review problems in the following areas. a. Nuclear power plant operations b. Nuclear engineering c. Chemistry and radiochemistry d. Metallurgy e. Nondestructive testing f. Instrumentation aid control g. Radiological safety h. Mechanical and electrical engineering i. Administrative controls j. Environmental k. Quality assurance practices QUALIFICATIONS 6.5.2.3 The following minimum experience requirements shall be established for those persons involved in the independent off-site safety review and audit program: a. Chairman and Vice-Chairman-Bachelor of Science in engineering or related field and ten years related experience including five years involvement with operation and/or design of nuclear power plants. b. Member-Bachelor of Science in engineering or related field and five years related experience including three years involvement with operation and/or design of nuclear power plants. ALTERNATES 6.5.2.4 All alternate members shall be appointed in writing by the NGRC Chairman to serve on a temporary basis; however no more than two alternates shall participate as voting members in NGRC activities at any one time. CRYSTAL RIVER - UNIT 3 6-8 Amendment No. 5 1306 126
ADMINISTRATIVE CONTROLS RECORDS 6.5.2.11 Records of NGRC activities shall be prepared, approved and distributed as indicated below: a. Minutes of each NRCC meeting shall be prepared, approved and forwarded to the Senior Vice President Engineering and Con-struction within 14 days following each meeting, b. Reports of reviews encompassed by Section 5.5.2.8 above, shall be prepared, approved and forwarded to the Senior Vice President-Engineering and Construction within 14 days following completion of the review. c. Audit reports encompassed by Section 6.5.2.9 above, shall be forwarded to the Senior Vice President Engineering and Construc-tion and to the management positions responsible for the areas audited within 30 days after completion of the audit. 6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken for REPORTABLE OCCURRENCES: a. The Commission shall be notified ar.d/or a report submitted pursuant to the requirements of Specification 6.9. b. Each REPORTABLE OCCURRENCE requiring 24 hour notification to the Commission shall be reviewed by the PRC and submitted to the NGRC and the Mana ar, Nuclear Operations. s
- CRYSTAL RIVER - UNIT 3 6-11 Amendment No. 5,26 l
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ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated: a. The facility shall be placed in at least HOT STANDBY witnin one hour. b. The Safety Limit violation shall be reported to the Commission, the Manager, Nuclear Operations and to the NGRC within 24 hours. c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence. d. The Safety Limit Violation Report shall be submitted to the Commission, the NRCC and the Manager, Nuclear Operations within 14 days of the violation. 6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and main-tained covering the activities referenced below: a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November, 1972. b. Refueling operations. c. Surveillance and test activities of safety related equipment. d. Security Plan implementation. e. Emergency Plan implementation. f. Fire Protection Program implementation. 6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by the PRC and approved by the Nuclear Plant Manager prior to, implementation and reviewed periodically as set forth in administrative procedures. CRYSTAL RIVER - UNIT 3 6-12 AmendmentNo.5,//,25 4 1306 128
ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORT 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Manage-ment Information and Program Control, U.S. Nuclear Regulatory Comis-sion, Washington, D.C. 20555, with a copy to the Regional Office, submitted no later than the 15th of each month following the calendar month covered by the report. REPORTABLE OCCURRENCES 6.9.1.7 The REPORTABLE OCCURRENCES of Specifications 6.9.1.8 and 6.9.1.9 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date. PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 6.9.1.8 The types of events listed below shall be repo ted within 24 hours by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the Regional Office, or his designate no later than the first working day following the event, with a written followup report within 14 days. The written followup report shall include, as a minimum, a completed copy of a licensee event report form. Information provided on the licensee event report fonn shall be supple-mented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event. a. Failure of the reactor protection system or other systems subject to limiting safety-system settings to initiate the required protective function by the time a monitored parameter reaches the setpoint specified as the limiting safety-system setting in the technical specifications or failure to complete the required protective function. b. Operation of the unit or affected systems when any paraneter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the limiting condition for operation established in the technical specifications. c. Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment. CRYSTAL RIVER - UNIT 3 6-15 Amendment ':o. 9 1306 129
ADMINISTRATIVE CONTROLS d. Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady-state conditions during power operation greater than or equal to 1% ak/k; a calculated reactivity balance indicating a shutdown margin less conservative than specified in the technical specifica-tions; short-term reactivity increases that correspond to a reactor startup rate of greater than 5.2 DPM or, if subcritical, an unplanned reactivity insertion of more tnan 0.5% ak/k; or occurrence of any unplanned criticality. e. Failure or malfunction of one or more components which prevents or could prevent, by itself, the fulfillment of the functional requirements of system (s) used to cope with accidents analyzed in the SAR. f. Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional requirements of systems required to cope with accidents analyzed in the SAR. g. Conditions arising from natural or man-made eveilts that, as a direct result of the event, require plant shutdown, operation of safety systems, or other protective measures required by technical specifications. h. Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or could have permitted reactor opera-tion in a manner less conservative than assumed in the analyses, i. Performance of structures, systems, or components that re-quires remedial action or corrective measures to prevent operation in a manner less conservative than that assumed in the accident analyses in the safety analysis report or tech-nical specifications bases; or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition. THIRTY-DAY WRITTEN REPORT 6.9.1.9 The types of events l'isted below shall be the subject of written reports to the Director of the Regional Office within 30 days of CRYSTAL RIVER - UNIT 3 6-16 Amendment No. 9, 2 5
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5-1 5.0 ADMINISTRATIVE CONTROLS Objective To define the organization, assign responsibilities, describe the environmental surveillance procedures, provide for a review and audit function, and prescribe the reporting requirements in order to insure continuing protection of the envi ronment and implement the Environmental Technical Specifications. 5.1 ORGANIZATICN The organization responsible for envircr: rental prctection, envi-ronmental monitoring and the implementation of the Envi ronmental Technical Specifications for Crystal River Unit 3, is shown on l Figure 5.1-1. 5.2 RESPONSIBILITY The r.ponsibility for the conduct of the precperational envi ron-mental monitoring program described in Section 3 and special studies described in Section 4 is that of the Quality and Environ-mental Department under the direction of the Director of Environ-mental and Licensing Affairs. The responsibility for the conduct l of the operational environmental monitoring program and the imple-mentation of Environmental Technical Specifications is the l responsibility of the Power Production Department. The plant organization is responsible for the development of Oper-ati ng and Surveillance Procedures described generally in Sec-tion 5.5 and supplying field data to the Manager, Nuclear Support l Services as required by Sections 2, 3 and 4 of the Environmental Technical Specifications. The Manager, Nuclear Support Services is responsible for consul-l tant contracts, State and local regulatory agreements, assembly of data, preparation and review of reports requi red by Section 5.6 of these Envi ronmental Technical Specifications, and m.aki ng recommen-dations to improve environmental protection practices. All reports and correspondence with the NRC regaMing the Environ-mental Technical Specifications shall be aparevec and signed by the Manager, Nuclear Operations. The Nuclear Plant Manager shali, however, man reports by telephere and telegracn of any incicent or cccurrence recuid ng recor:ing wi:nin 24 neurs er less, as requi red i n Seetion 5.5. IP6 131 Amendment No. 2 5
5-2 D* 0 '"' D T) @ W W PRESIDENT SENCR VICE ARES. SEMICR VICE PRES. bN 8 GEN. COO.NSEL 8 CCN TRU ASST. V!CE PRES. VICE PRESICENT ENVIRCNMENT p[$8,g & NEW TECNNQ.OGY DIRECTOR ENVIRO N M ENT 8 MANAGER MANAGER PRC00CTICN NUCLEAR OPERATIONS SERVICES NUCLEAR ~ MANAG R MANAGER NUCLEAR SF,RT SERVICES PLANT STAFF FIGURE
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5-3 5.3 REVIEW AND AUDIT 5.3.1 Function The Nuclear General Review Coninittee shall function to provide independent review and audit of designated activities in the areas of environmental monitoring and surveillance. 5.3.2 Composi tion The NGRC shall be composed of the Chairman, Vice Chairman, and at least 5 members. No more than a minority of the members shall have line responsibility for operation of the facility. The committee shall collectively have the experience and com-petence required to review problems in the following areas: a. Nuclear power plant o; rr.tions o. Nuclear engineering c. Chemistry and radiochemistry d. Metallurgy e. Nondestructive testing f. Instrumentation and control g. Radiological safety h. Mechanical and electrical engineering i. Administrative controls j. Envi ronmental k. Quality assurance practices 5.3.3 Oualifications The following minimum experience requirements shall be established for those persons involved in the independent off-site safety review and audit program: a. Chairman and Vice-Chairman-Bachelor of Science in engineering or related field and ten years relatec experience including five years involvement witn operation and/or design of nuclear power plants. b. Member-Bachelor of Science in engineering or related field and five years related experience including three years involvement with operation and/or design of nuclear power plants. Amendment No. '.E } b l33 4. PRESIDENT SENICR SENIOR NUCLEAR VICE PRES 3 CENT VICE PRESICENT GENERAL REVIEW CCAPCRATE SERvlCES ENGINEERING & CCNS RUCTION CCMMITTEE a 3E sgs.AL COUNSEL ASST vlCE POESICENT PLANT VICE PRESIDENT PCWER REVI EW ENVIRONMENT PRCCUCTICN COMMITTEE S NEW TECHNOWGY DIRECTOR MANAGER QUALITY NUCLEAR PROGRAMS CPERATICNS 13 6 34 FI G. S.3 1 CR GA NI* ATIO N FCR lNCEPENCENT REVIEW ANC AUCIT. Amendment No. 2 5
5-4a 5.3.4 Alternates All alternate members shall be appointed in writing by the fiGRC Cha'irman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in NGRC activities at any one time. 5.3.5 Consul tants Consultants shall be utilized as determined by the NGRC Chairman to provide expert advice to the NGRC. 5.3.6 Meeting Frequency The NGRC shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter. 5.3.7 Ouorum A quorum of fGRC snall consist of the Chairman or nis designated alternate and five additional NGRC members, including alternates. No more than a minority of the quorum shall have line responsi-bility for operation of the facility. 5.3.8 Review The NGRC shall revia, a. Proposed changes to the Environmental Technical Specifications and the evaluated impact of the changes, b. Proposed changes or modifications to plant systems or equipment and the evaluated impact which would require a change in the procedures described in 5.5.1 below (or which would affect the evaluation of the plant's environmental impact) as determined by the Plant Review Committee. c. Reported instances of violations of Environmental Technical Specifications, the reaching of specified reporting levels, and reportable environmental occurrences. d. Proposed special tests or experiments which might involve a change in the Environmental Technical Specifications or involve an unreviewed environmental impact cuestion. e. Temporary changes to procedures as described in 5.5.2. f. Events requiring 24 hour notification to the Ccmmssion. g. Descriptions of changes, tests or experiments, and the results thereof, as described in 5.5.3.a. Amendment No. 2c 13 6 135
5-4b h. Audits of the environmental monitoring and sur-veillance : agram. 5.3.9 Audi ts Audits of facility activities shall be performed under the cognizance of the f4GRC. These audits shall encompass: a. Implementation of the environmental monitoring and surveillance programs at least once per twelve months. b. Conformance to procedures and ETS requirements at least once per twelve months. c. Contractor environmental monitoring and sur-veillance activities at least once per twelve months. 5.3.10 Records Records of riGRC activities shall be prepared, approved and .fistributed as indicated below: a. Minutes of each riGRC meeting shall be prepared, approved and forwarded to the Senior Vice President Engineering and Construction within 14 days following each meeting, b. Reports of reviews encompassed by Section 5.3.8 above, shall be prepared, approved and forwarded to the Senior Vice President Engineering and Construction within 14 days following completion of the review, c. Audit reports encompassed by Section 5.3.9 above, shall be forwarded to the Senior Vice President Engineering and Construction and to the management positions responsible for the areas audited within 30 days after completion of the audit. 5.3.11 Authority The tiGRC shall report to and advise the Senior Vice President Engineering and Construction on those areas of responsibility specified in Sections 5.3.8, 5.3.9 arm 5.3.10 (see Figure 5.3-1). 13o6 136 Amendment flo. 2 5 4
5-5 5.4 ACTION TO BE TAKEN IF LIMITING CONDITION FOR OPERATION IS EXCEEDED 5.4.1 Immediate remedial actions as pemitted by these environmental technical specifications shall be implemented until such time as the limiting condition for operation is met. 5.4.2 The occurmnce shall be promptly reported to the Chai rman of the Nuclear General Review Committee and investigated as specified in Section 5.3. 5.4.3 The Nuclear General Review Committee shall prepare and submit a report for each occurrence in accordance with Section 5.3.10. 5.4.4 The Manager, Nuclear Operations, shall report the occurrence to l the NRC as specified in Section 5.6.2. 5.5 PROCEDURES 5.5.1 Explicit written procedures, including applicable check-off lists and instructions, shall be prepared for the implementation of the monitoring requirements described in Sections 2 and 3, approved as specified in Section 5.5.2, and adhered to for operation of all systems and ccrnponents involved in carryi ng out the effluent release and environmental monitoring programs. Procedures shall include sampling, instrument calibration, analysis, and action to be taken when limits am approached or exceeded. Calibration fre-quencies and standards for instruments used in perfomi ng the measurements shall be included. Testing frequency of alarms shall be included. These frequencies shall be determined fr:rn experi-ence with similar instruments in similar environments and from manufactumrs' technical manuals. 5.5.2 All procedures implemented by plant staff personnel described in Section 5.5.1 above, and changes thereto, shall be reviewed as specified in Section 5.3 and approved by the Nuclear Plant Manager l prior to implementation. Temporary changes to procedures #11ch do not change the intent of the original procedure may be made, pro-vided such changes are approved by two memcers of the plant man-agement staff, one of whom holds a senior operator's license. Such changes shall be documented, subsequently reviewed anc approved by the Plant and Nuclear General Review Committees. All procedures and changes to procedures utilized by contractors to implement tne environmental monitoring prograns described in Section 3 snall be reviewed and approved by the Manager, Nuclear Suppor. Ser/ ices. Amendment No. 2f, i
5-6 5.5.3 Prior to special tests or changes: a. If the Nuclear Plant Manger d. ides to make a change in the facility or Operating Procedures, or to conduct a test or experiment, and concludes that the proposed change, test, or experiment does not involve a change in the Environmental Technical Specifications or an unreviewed environmental impact question, he may order the change, test or experiment to be made, shall enter a description thereof in the operating records of the facility, and shall send a copy of the instructions pertinent thereto to the Chairman of the. Nuclear General Review Committee for review per Section 5.3.8. b. If the Nuclear Plant Manager desires to make a l change in the facility or Operating Procedures, or to conduct a test or experiment which in his opinion might involve a change in the Environmental Technical Specifications, or involve an unreviewed environmental impact question, he shall not order such change, test or experiment until he has referred the matter to the Nuclear General Review Cormittee for review and report to the Senior Vice President Engineering and Construction for resolution. 5.6 PLANT REPORTING REQUIREMENTS 5.6.1 Routine Recorts A. Annual Environmental Oceratinc Recort (1) Non radiological Volume A report on the nonradiological environmental surveillance programs for the previous 12 months of operation shall be 13o6 138 Amendment,No.25 ,}}