ML19319D632
| ML19319D632 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/05/1977 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19319D629 | List: |
| References | |
| NUDOCS 8003180668 | |
| Download: ML19319D632 (17) | |
Text
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r' FIDRIDA POWER CORPORATION CITY OF ALACHUA CITY OF BUSHNELL CITY OF GAINESVILLE CITY OF KISSIMEE CITY OF LEESBURG l
CITY OF NEW SMYRNA BEACH AND UTILITIES COMISSION, CITY OF NEW SMYRNA BEACH CITY OF OCALA ORLANDO UTILITIES COMISSION AND CITY OF ORLANDO SEBRING UTILITIES COMMISSION SEMINOLE ELECTRIC COOPERATIVE, INC.
CITY OF TALLAHASSEE DOCKET NO. 50-302 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT AMENDMENP TO FACILITY OPERATING LICENSE l
Amendment No. 5 License No. DPR-72 I
I 1.
The Nuclear Regulatory Comission (the Comission) having found that:
I A.
The application for amendment by Florida Power Corporation, et al (the licensees) dated May 20, 1977, 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 operete 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 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 requirmnents have been satisfied.
8003180.
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r 2.
Specifications as indicated in the attachment amendment and paragraph 2.C(2) of facility Operating License No. DPR-72 is hereby amended to read as follows:
2.C.(2) _ Technical Specifications The Technical Specifications contained in Appendices A and as revised through Amendment No. 5, are hereby incorporate the license.
facility in accordance with the Technical Specifi 3.
This license amendment is effective as of the date o ce.
MR THE NUCLEAR REGUIRIORY cot @iIS
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(.
r o b F. Stolz, Chief
/L ht Water Reactors Branca No. I d) vision of Project Mangament
Attachment:
Changes to the Technical Specifications i
Date of Issuance: JUL 0 51977 b
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JUL 0 51977 ATTACHMENT TO LICENSE AMENDMENT NO. 5 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO. 50-302 Replace the following pages of the Appendix "A" Technical Specifications The revised pages are identified by Amendment with the enclosed pages.
The number and contain vertical lines indicating the area of change.
corresponding overleaf pages are also provided to maintain document completeness.
Pages 6-1 6-2 6-3 6-5 6-6 6-7 6-8 6-10 6-11 6-12 6-13 l
l l
6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Nuclear Plant Manager shall be responsible for overall l
facility operation and shall delegate in writing the succession to this responsibility during his absence.
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:
Each on duty shift shall be composed of at least the minimum a.
shift crew composition shown in Table 6.2-1.
b.
At least one licensed Operator shall be in the contrc. 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 from 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 respor,sibilities during this operation.
l CRYSTAL RIVER - UNIT 3 6-1 Amendment No. 5
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5 CRYSTAL RIVER - UNIT 3 6-2 Amendment No. 5
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NUCLEAR PLANT I
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Figure 6.2 2 Facility Orgentration un
TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION #
LICENSE APPLICABLE MODES CATEGORY 1, 2, 3 & 4 5&6 SOL 1
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OL 2
1 Non-Licensed 3
1
- Does not include the licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling Individual supervising CORE ALTERATIONS after the initial fuel loading.
- Shift crew composition may be less that the minumum require-ment 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 accomodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 6.2-1.
l f
CRYSTAL RIVER - UNIT 3 6-4
ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF QUALIFICATIONS 5 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 Radiation Protection Engineer who shall meet or exceed 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 Assistant Nuclear Plant Manager and shall meet or exceed the requirements and recomendations l
of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
6.5 REVIEW AND AUDIT 6.5.1 DLANT REVIEW COMMITTEE (PRC)
FUNCTION 6.5.1.1 The Plant Review Comittee shall function to advise the Nuclear Plant Manager on all matters related to nuclear safety.
l C_0MPOSITION 6.5.1.2 The Plant Review Comittee shall be composed of the:
Chaiman:
Assistant Nuclear Plant Manager l
Member:
Operations Supervisor Member:
Technical Support Engineer Member:
Maintenance Engineer Member:
Chemistry and Radiation Protection Engineer ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PRC Chaiman to serve on a temporary basis; however, 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 Chariman or his designated alternate.
CRYSTAL RIVER - UNIT 3 6-5 Amendment No. 5
~
ADMINISTRATIVE CONTROLS QUORUM 6.5.1.5 A quorum of the PRC shall consist of the Chariman or his designated alternate and four members including alternates.
RESPONSIBILITIES 6.5.1.6 The Plant Review Comittee shall be responsbile for:
Review of 1) all procedures required by Specification 6.8 and a.
changes thereto, 2) any other proposed procedures or changes thereto as detemined by the Nuclear Plant Manager to affect l
nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear Safety.
Review of all proposed changes to the Appendix "A" Technical c.
Specifications.
d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
Investigation of all violations of the Technical Specifications e.
including the preparation and forwarding of reports covering evaluation and recomendations to prevent recurrence to the Director-Power Production and to the Chairman of the Nuclear
[
General Review Comittee.
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 Comission.
g.
Review of facility operations to detect potential nuclear safety hazards.
h.
Perfomance of special reviews, investigations or analyses and reports thereon as requested by the Chaiman of the Nuclear General Review Comittee.
1.
Review of the Plant Security Plan and implementing procedures and shall submit recomended changes to the Chaiman of the Nuclear General Review Comittee.
j.
Review of the Emergency Plan and implementing procedures and shall submit recomended changes to the Chairman of the Nuclear General Review Comittee.
CRYSTAL RIVER - UNIT 3 6-6 Amendment No. 5
ADMINISTRATIVE CONTROLS
,5 AUTHORITY
'.5.1.7 The Plant Review Comittee shall:
,.f 8
6 a.
Recomend to the Nuclear Plant Manager written approval or l
disapproval of items considered under 6.5.1(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 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Director-Power Production and the Nuclear General Review Comittee 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 Comittee shall maintain written minutes of each meeting and copies shall be provided to the Director-Power Produc-
[
tion and Chairman of the Nuclear General Review Comittee.
i 6.5.2 NUCLEAR GENERAL REVIEW COMMITTEE (NGRC)
FUNCTION 6.5.2.1 The Nuclear General Review Comittee shall function to provide b
independent review and audit of designated activities in the areas of:
j a.
Nuclear power plant operations b.
Nuclear engineering i.,3 c.
Chemistry and radiochemistry d.
Metallurgy
>d i
e.
Instrumentation and control f.
Radiological safety g.
Mechanical and electrical engineering b
t h.
Quality assurance practices '
CRYSTAL RIVER - UNIT 3 6-7 Amendmeit No. 5 m
i
~ ADMINISTRATIVE CONT.~tS COMPOSITION 6.5.2.2 The NGRC shall be composed of the Chairman, Vice Chainnan, and at least 5 members. No n. ore 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 and control g.
Radiological safety j
h.
Mechanical and electrical engineering 1.
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:
6.
Chainnan and Vice-Chaiman-Bachelor of Science in eng'.neering 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 desi'gn 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
ADMINISTRATIVE CONTROLS CONSULTANTS 6.5.2.5 Consultants'shall be utilized as determined by the NGRC Chairman
'to provide expert advice to the NGRC.
MEETING FREQUENCY 6.5.2.6 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.
QUORUM j
6.5.2.7 A quorum of NGRC shall consist of the Chairman or his designated alternate and five additional NGRC members, including alternates.
No more than a minority of the quorum shall have line responsibility for cperation of the facility.
REVIEW 6.5.2.8 The NGRC shall review:
The safety evaluations for 1) changes to procedures, equipment a.
or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.
b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59,10 CFR.
Proposed tests or experiments which involve an unreviewed c.
safety question as defined in Section 50.59, 10 CFR.
d.
Proposed changes in Technical Specifications or this Operating License..
Violations of codes, regulations, orders, Technical Specifications, e.
license requirements, or of internal procedures or instructions having nuclear safety significance, f.
Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.
I i
CRYSTAL RIVER - UNIT 3 6-9
ADMINISTRATIVE CONTROLS REVIEW (Continued) g.
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.
h.
Al' recognized indications of an unanticipated deficiency in sc=a aspect of design or operation of safety related structures, systems, or components, i.
Reports and meetings minutes of the Plant Review Committee.
AUDITS 6.5.2.9 Audits of facility activities shall be performed under the cognizance of the NGRC.
These audits shall encompass:
The conformance of facility operation to provisions containcd a.
within the Technical Specifications and applicable license conditions at least once per 12 months.
b.
The performance, training and qualifications of the entire facility staff at least once per 12 months.
The results of actions taken to correct deficiencies occurring c.
in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.
d.
The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 months.
j The Facility Emergency Plan and implementing procedures at e.
1 east once per 24 months.
1 f.
The Facility Security Plan and implementing procedures at least once per 24 months.
Any other area of facility operation considered appropriate by j
g.
the NRCC or the Senior Vice President-Engineering and Construction.
AUTHORITY 6.5.2.10 The NGRC shall report to and advise the Senior Vice President-Engineering and Construction on those areas of responsibility specified l
in Sections 6.5.2.8 and 6.5.2.9.
CRYSTAL RIVER - UNIT 3 6-10 Amendment No. 5 i
ADMINISTRATIVE CONTROLS RECORDS 6.5.2.11 Records of NGRC activities shall be prepared, approved and distributed as indicated below:
Minutes of each NRCC meeting shall be prepared, appioved and a.
forwarded to the Senior Vice President-Engineering and Construc-tion within 14 days following each meeting.
b.
Reports of reviews encompassed by Section 6.5.2.8 above, shall be prepared, approved and forwarded to the Senior Vice President-Engineering and Construction within 14 days following completion I
of the review.
Audit reports encompassed by Section 6.5.2.9 above, shall be c.
forwarded to the Senior Vice-President Engineering and Construction [
8 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 and/or a report submitted pursuant to the requirements of Specification 6.9.
b.
Each REPORTABLE OCCURRENCE requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notification to the Commission shall be reviewed by the PRC and submitted to the NGRC and the Director-Power Production.
I i
CRYSTAL RIVER - UNIT 3 6-11 Amendment No. 5
ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
The facility shall be placed in at least HOT STANDBY within a.
one hour.
b.
The Safety Limit violation shall be reported to the Commission, the Director-Power Production and to the NGRC within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I 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.
l d.
The Safety Limit Violation Report shall be submitted to the Commission, the NRCC and the Director-Power Production within l
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.
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 I
as set forth in administrative procedures.
CRYSTAL RIVER - UNIT 3 6-12 Amendment No. 5
ADMINISTRATIVE CONTROLS 6.8.3 Temporary changes to procedures.of 6.8.1 above may be made provided:
a.
The intent of the original procedure is not alterad.
b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected.
The change is documented, reviewed by th'e PRC and approved by c.
the Nuclear Plant Manager within 14 days of implementation.
l 6.9 REPORTING REQUIREMENTS
_0lAINE REPORTS AND REPORTABLE OCCURRENCE REPORTS R
6.9.1 Information to be reported to the Comission, in addition to the reports required by Title 10, Code of Federal Regulations, shall be in accordance with the Regulatory Position in Revision 4 of Regulatory Guide 1.16, " Reporting of Operating Information - Appendix "A" Technical Sprei fications."
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement, Region II, within the time period specified for each report.
These repoets shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference i
specification:
ECCS Actuation, Specifications 3.5.2 and 3.5.3.
a.
b.
Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.
Inoperable Meteorological Monitoring Instrumentation, Specifi-c.
cation 3.3.3.4.
f d.
Seismic event analysis, Specification 4.3.3.3.2.
f CRYSTAL RIVER - UNIT 3 6-13 Amendment No. 5
ADMINISTRATIVE ~ CONTROLS
.6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:
a.
Records and logs of facility operation covering time interval at each power level.
b.
Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of er,uipment related to nuclear safety.
c.
All REPORTABLE OCCURRENCES submitted to the Canmission.
d.
Records of surveillance activities, inspections and calibrations i
required by these Technical Specifications, e.
Records of reactor tests and experiments.
f.
Records of changes made to Operating Procedures.
g.
Records of radioactive shipments.
h.
Records of sealed source and fission detector leak tests and results.
i.
Records of annual physical inventory of all sealed source material of record.
6.10.2 TF1 following records shall be retained for the duration of the Facility Operating License:
a.
Records and drawing changes reflecting facility design modifi-cations made to systems and equipment described in the Final Safety Analysis Report.
b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
c.
Records of facility radiation and contamination surveys.
d.
Records of radiation exposure for all individuals entering radiation control areas.
CRYSTAL RIVER - UNIT 3 6-14
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