ML14183A304
| ML14183A304 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 03/31/1995 |
| From: | Bateman W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14183A305 | List: |
| References | |
| DPR-23-A-160 NUDOCS 9504070011 | |
| Download: ML14183A304 (19) | |
Text
6M RREG 0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-001 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 160 License No. DPR-23
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee), dated July 22, 1994, as supplemented March 6, 1995, 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-23 is hereby amended to read as follows:
9504070011 950331 PDR ADOCK 05000261
B. Technical SDecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 160, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
- 3.
This licens6 amendment is effective as of the date of its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION William H. Bateman, irector Project Directorate II-I Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 31, 1995
ATTACHMENT TO LICENSE AMENDMENT NO. 160 FACILITY OPERATING LICENSE NO. DPR-23 DOCKET NO. 50-261 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
'Remove Pages Insert Pages 6.5-3 6.5-3 6.5-5 6.5-5 6.5-6 6.5-6 6.5-7 6.5-7 6.5-7a 6-5-7a 6.5-8 6.5-8 6.5-9 6.5-9 6.5-10 6.5-10 6.5-11 6.5-11 6.5-12 6.5-12 6.5-13 6.5-13 6.5-14 6.5-14 6.5-15 6.5-15 6.6-1 6.6-1 6.7-1 6.7-1 6.10-2 6.10-2
assure Ot the reviewers collectively piess the background and qualifications in the disciplines necessary and important to the specific review. The list will include the disciplines for which each person is qualified.
6.5.1.1.5 Temporary changes to'procedures, tests, or-experiments may be approved by two members of the plant staff, at least one of whom holds a Senior Reactor Operator License if such change does not change the intent of the original procedure, test, or experiment. Temporary changes shall be documented and.
within 21 days of receiving temporary approval, be reviewed in accordance with Specifications 6.5.1.1.2, 6.5.1.1.3, and 6.5.1.1.4 and incorporated as a permanent change or deleted.
6.5.1.1.6 Those procedures, tests, or experiments and changes thereto that constitute an unreviewed safety question, or involve a change to Technical Specifications.shall be reviewed by the Plant Nuclear Safety Committee and submitted to the NRC for approval prior to implementation. All such procedures, tests, or experiments and changes shall be reviewed by the Nuclear Assessment Section prior to implementation.
6.5.1.1.7 Procedures, tests, or experiments, which constitute a change to the facility as described in the UFSAR shall also be reviewed by the Nuclear Assessment Section. These reviews may be conducted after plant Management approval, and implementation may proceed prior to completion of review as provided for by 10 CFR 50.59(a)(1).
6.5.1.2 Modifications 6.5.1.2.1 A safety analysis shall be prepared for all modifications that affect nuclear safety. The analysis shall include a-:
written determination of whether or not the modification is a change in the facility as described in the UFSAR, involves a change to the Technical Specifications, or constitutes an unreviewed safety question as defined in 10 CFR 50.59(a)(2).
6.5-3 Amendment No.84.138 160
6'5.1.2.4 Modifica s that are determined to eith onstitute an unreviewed safety question, as defined in 10 CFR 50.59(a)(2). or a change to the Technical Specifications. shall be reviewed by the Plant Nuclear Safety Committee and submitted to the NRC for approval prior to implementation. All such modificationsshall be approved by the Nuclear Assessment Section prior to implementation.
6.5.1.2.5 Modifications which constitute changes to the facility as described in the FSAR shall also be reviewed by the Nuclear Assessment Section. This review may be conducted after plant management approval, and implementation may proceed prior to completion of review.
6.5.1.3 Technical Specifications and License Changes 6.5.1.3.1 Each proposed Technical Specification or Operating License change shall be reviewed by the Plant Nuclear Safety Committee and submitted to the NRC for approval.
6.5.1.4 Review of Technical Specification Violations 6.5.1.4.1 All violations of Technical Specifications shall be investigated and a report prepared that evaluates the event and that provides recommendations to prevent recurrence. Such reports shall be reviewed by the Plant Nuclear Safety Committee and approved by the Plant General Manager or his designee and submitted to the Vice President Robinson Nuclear Plant and to the Manager - Nuclear Assessment Section.
6.5.1.5 Nuclear Safety Review Qualification 6.5.1.5.1 Individuals shall be designated by the Vice President Robinson Nuclear Project for the safety reviews of Specifications 6.5.1.1.2. 6.5.1.1.3, 6.5.1.2.1. and 6.5.1.2.2. These reviewers shall have a Bachelor of Science in engineering or related field or equivalent and:two years related experience.
6.5-5 Amendment No. $9, 160
6-.5.1.6 Plant Nugar Safety Committee (PNSC) 6.5.1.6.1
- a.
As an effective means for the regular overview.
evaluation, and maintenance of plant operational safety, a Plant NuclearSafety Committee (PNSC) is established.
b.-
The committee shall function, through the utilization of subcommittees, audits, investigations, reports, and/or performance of reviews as a group, to advise the General Manager on all matters related to nuclear safety.
6.5.1.6.2 The PNSC shall be composed of a Chairman and seven to nine members. The members shall be from the following functional areas.
Operations Maintenance Engineering Health Physics/Chemistry Regulatory Affairs Nuclear Assessment 6.5.1.6.3 The PNSC Chairman, alternate Chairmen, members, and alternate members shall be designated in writing by the plant General Manager.
Members shall be individuals who are unit manager level or above from the site management organization.
Alternate members shall, as a minimum, meet equivalent qualification criteria as specified in Section 4.4 of ANSI N18.1-1971 for professional technical personnel.
6.5.1.6.4a The quorum of the PNSC necessary for the performance of the activities of these Technical Specifications shall consist of the Chairman (or his designated alternate) and four members (-Uncluding alternates).
6.5.1.6.4b.No more than two alternates shall be counted toward meeting the quorum requirement or participate as voting members of the PNSC at any one time.
6.5.1.6.5 The PNSC shall meet at least once per calendar month and as convened by the PNSC Chairman or his designated alternate.
6.5-6 Amendment No.9tX0,778 160
6.5.1.6.6 The PNS*
tivities shall include the fo*4ing:
a)
Perform an overview of Specifications 6.5.1.1 and 6.5.1.2 to assure that processes are effectively maintained.
b)
Performance of special reviews. investigations, and reports thereon requested by the Manager - Nuclear Assessment Section.
c)
Annual review of the Security Plan and Emergency Plan.
d)
Perform reviews of Specifications 6.5.1.1.6, 6.5.1.2.4, 6.5.1.3.1. and 6.5.1.4.1.
e)
Perform review of all reportable events.
f)
Review of facility operations to detect potential nuclear safety hazards.
g)
Review of every unplanned on site release of radioactive material to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrences to the Vice President - Robinson Nuclear Plant.
h)
Review of changes to the Process Control Program and the Offsite Dose Calculation Manual.
i)
Review of major changes to radioactive liquid, gaseous, and solid waste treatment systems.
j)
Review of changes to the CORE OPERATING LIMITS REPORT.
k)
Annual review of the Fire Protection Program, including Program changes.
6.5-7 Amendment No. ;42.160
6-.5.1.6.7 In the eA t of disagreement between the *oommendations of the Plant Nuclear Safety Committee and the actions contemplated by the General Manager, the course determined by the General Manager to be more conservative will be followed. The Vice President - Robinson Nuclear Plant will be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the, disagreement and subsequent actions.
6.5.1.6.8 The PNSC shall maintain written minutes of each meeting that, at a minimum, document the results of all PNSC activities performed under the provisions of these Technical Specifications; and copies shall be provided to the Vice President - Robinson Nuclear Plant and to the Manager - Nuclear Assessment Section.
6.5-7a Amendment No. 1
6.5.2 Nuclear Assesgnt Section Independent Review Oiram 6.5.2.1 FUNCTION The Nuclear Assessment Section shall function to provide independent review of plant changes, tests, and procedures. In addition, the independent review function will verify that reportable events are investigated in a timely manner and corrected in a manner that reduces the probability of recurrence of such events and detect trends that may not be apparent to a day-to-day observer.
6.5.2.2 ORGANIZATION 6.5.2.2.1 The individuals assigned responsibility for independent reviews shall be qualified in specific disciplines. These individuals shall collectively have the experi.ence and competence required to review activities 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 h) mechanical and electrical engineering i) administrative controls j) seismic and environmental k) quality assurance practices
- 1) other appropriate fields 6.5.2.2.2 The Manager - Nuclear Assessment Section shall have a bachelor's degree in an engineering or related field and, in addition, shall have a minimum of ten years' related experience, of which.five years shall be in the operation and/or design of nuclear power plants.
6.5.2.2.3 The individuals performing independent safety reviews shall have a bachelor's degree in an engineering or related field or equivalent and, in addition, shall have a minimum of five years' related experience.
6.5-8 Amendment NoAWig 160
6.5.2.2.4 An indiOial may possess competence in g than one specialty area. If sufficient expertise is not available within the Nuclear Assessment Section, competent individuals from other CP&L organizations or outside consultants shall be utilized in performing independent reviews and investigations.
6.5.2.2.5 The documents submitted under 6.5.2.3 shall be reviewed by individuals meeting the requirements of 6.5.2.2.1 and 6.5.2.2.3 to ensure all applicable disciplines are encompassed. Multiple reviews will be conducted on documents where required to meet applicable disciplines of 6.5.2.2.1.
6.5.2.2.6 Independent safety reviews shall be performed by individuals not directly involved with the activity under review or responsible for the activity under review.
6.5.2.2.7 The Nuclear Assessment Section Independent Safety Review Program shall be conducted in accordance with written, approved procedures.
6.5.2.3 REVIEW Nuclear Assessment Section shall perform reviews of the following:
- a.
Written safety evaluations of changes in the facility as described in the UFSAR, changes in procedures as described in the UFSAR. and tests or experiments not described in the UFSAR which are completed without prior NRC approval under the provisions of 10 CFR 50.59(a)(1). These reviews are to verify that such changes, tests, or experiments do not involve.a change in the Technical Specifications or an unreviewed safety question as defined in 10 CFR 50.59(a)(2).
These reviews may be conducted after appropriate management approval, and implementation may proceed prior to completion of the review.
- b.
Proposed changes in procedures required by these Technical Specifications, proposed changes in the facility, or proposed tests or experiments, any of which involve a change in the Technical Specifications or an unreviewed safety question pursuant to 10 CFR 50.59(a)(2) prior to implementation.
- c.
Proposed changes to the Technical Specifications or this Operating License prior to implementation.
6.5-9 Amendment No.
d Vi~tions, deviations, and reportW events, which require reporting to the NRC in writing, such as:
- 1.
violations of applicable codes, regulations, orders, TechnicalSpecifications. license requirements, or internal procedures or instructions have safety significance:
- 2.
significant operating abnormalities of deviations from normal or expected performance of plant safety-related structures, systems, or components; and
- 3.
reportable events, as specified in 10 CFR 50.73.
- e.
Any other matter involving safe operation of the nuclear power plant that the Manager - Nuclear Assessment Section deems appropriate for consideration or which is referred to by the Manager - Nuclear Assessment Section by the on-site operating organization. PNSC, or by other functional organizational units within CP&L.
6.5.2.4 RECORDS (a) Results of Nuclear Assessment Section independent safety reviews shall be documented and retained.
6.5-10 Amendment No.8, 160
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6.5-11 Amendment No. 1M,160
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6.5-12 Amendment No.70,13,160
6.5.3 Nuclear @essment Section Assessment Prtm 6.5.3.1 Assessments of facility activities shall be performed by the Nuclear Assessment Section. Assessments will be performance based 6and will be scheduled based on plant performance and importance to safety but at a frequency not to exceed 24-months. These assessments shall encompass:
- a.
The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions.
- b.
The performance, training and qualifications of the entire facility staff.
- c.
The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety.
- d.
The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix B. 10 CFR
- 50.
- e.
Any other area of facility operation considered appropriate by the Vice President - Robinson Nuclear Plant.
- f.
The Radiological Environmental Monitoring Program and the results thereof.
- g.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures.
- h.
The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes.
6.5.3.2 Assessments of activities prescribed by the Code of Federal Regulations will be performed at the frequencies prescribed by the applicable regulation. These assessments shall encompass:
- a.
Emergency Preparedness (per 10 CFR 50.54(t))
- b.
Security (per 10 CFR 50.54(pY)
- c.
Radiation Protection (per 10 CFR 20.1101) 6.5-13 Amendment No. 84,18,16(
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W 6.5-14 Amendment No. 04U,160
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6.5-15 Amendment No. $5 JO$ 1 160
6.6 REPORTABLE EV@g ACTION 6.6.1 The following actions shall be taken for events requiring immediate notification:
a)
The NRC shall be notified pursuant to the requirements of 10 CFR 50.72.
b)
Each reportable event shall be reviewed in accordance with Specification 6.5.1.6.6 and submitted to the Manager - Nuclear Assessment Section. and the Vice President - Robinson Nuclear Plant.
6.6.2 The following actions shall be taken for reportable events requiring a Licensee Event Report:
a)
A report shall be submitted to the NRC pursuant to the requirements of 10 CFR 50.73.
b)
Each reportable event shall be reviewed in accordance with Specification 6.5.1.6.6 and submitted to the Manager - Nuclear Assessment Section, and the Vice President - Robinson Nuclear Plant.
6.6-1 Amendment No. $9,774,12 160
6.7 SAFETY LIMIT V#TION 6.7.1 The following actions shall be taken in the event a safety limit is violated:
a)
The provisions of 10 CFR 50.12 shall be complied with.
b)
The provisions of 10 CFR 50.36(c)(1)(i) shall be complied with.
C)
The safety limit violation shall be reported to the NRC Region II within one hour and the Vice President - Robinson Nuclear Plant within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
d) A Safety Limit Report shall be prepared. The report shall be reviewed in accordance with Specification 6.5.1.6.6. 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.
e)
The Safety Limit Violation Report shall be submitted to the NRC. Vice President - Robinson Nuclear Plant, and the Manager - Nuclear Assessment Section within 14 days of the violation.
6.7-1 Amendment No. 160
- b.
- rds of new and irradiated fueloventory. 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.
- e.
Records of gaseous and liquid radioactive material released to the environs.
- f.
Records of transient or operational cycles for those facility components designed for a limited number of transients or cycles.
- g.
Records of training and qualification for current members 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 program.
- j.
Records of review performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10CFR50.59.
- k.
Records of meetings of the PNSC.
- 1.
Records of data results required by the radiological environmental monitoring program.
- m.
Records of Independent Reviews.
6.10-2 Amendment No.
1