ML14175A624
| ML14175A624 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 03/13/1980 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14175A625 | List: |
| References | |
| DPR-23-A-046 NUDOCS 8004280151 | |
| Download: ML14175A624 (16) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 CAROLINA-POWER AND LIGHT COMPANY DOCKET NO. 50-261 H. B. ROBINSON STEAM ELECTRIC PLANT UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
46 License No. DPR-23
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Carolina Power and Light Company (the licensee) dated November 7, 1979 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.
Q00O4280
-2
- 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:
B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 46, are hereby incor porated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of March 13, 1980.
FOR THE NUCLEAR REGULATORY COMMISSION A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: March 13, 1980
ATTACHMENT TO LICENSE AMENDMENT No.
46 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 pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Insert 6.1-1 6.1-1 6.2-3 (Figure 6.2-1) 6.2-3 (Figure 6.2-1) 6.1-3 (Figure 6.2-2) 6.2-4 (Figure 6.2-2) 6.4-1 6.4-1 6.5-1 6.5-1 6.5-2 6.5-2 6..5-3 6.5-3 6.5-4 6.5-4 6.5-9 6.5-9 6.5-12 6.5-12 6.6-1 6.6-1 6.7-1 6.7-1 6.8-1 6.8-1
6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The General Manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.
6.1-1 Amendment No.
46
CHAIRMAN OF THE BOARD PRESIDENT/
CHIEF EXECUTIVE OFFICER CHIEF OPERATING OFFICER SENIOR EXECUTIVE V.PRESIDENT POWER SUPPLY & CUSTOMER SERV.
EXECUTIVE VICE PRESIDENT POWER SUPPLY SENIOR VICE PRESIDENT NUCLEAR OPERATIONS NUCLEAR SAFETY &
DEPARTMENT RESEARCH VICE PRESIDENT VCE PRESIDENT NUCLEAR OPERATIONS CORPORATE NUCLEAR DEPARTMENT SAFETY & QUALITY STAFF ASSURANCE AUDIT SMANAGER PLANT GEN. MANAGER
..J PLANT NUCLEAR SAFETY COMMITTEE ADMINISTRATIVE ORGANIZATION OFF-SITE ORGANIZATION zOR
-- -------LINES OF COMMUICATION H.B. ROBINSON 2 MANAC-EM!ENT
.FIGULINESOFNAND. TECHNICAL SUPPORT FIGURE 6.2-1 6.2-3 Amendment No. 46
SRO -
SENIOR REACTOR OPERATOR LICENSE GENERAL MANAGER RO REACTOR OPERATOR LICENSE ROBINSON PLANT 4ANAG ER MANAGER DIRECTO OPERATION AND TECHNICAL AND NUCLEAR SA MAINTENANCE ADMINISTRATIVE AND Q.A SRO F
SUPERVISOR SAPERVISOR.
14AINENNCE ENGINEERING AD4INISTRATIVE AND RADIATION A SURANCE UNIT NO. 2 UNIT NO. 2 SUPERVISOR SUPERVISOR SUPERVISOR CONTROL SUPERVISOR SECURITY UNIT N0. I SUPERVi)0R OPERATIONS EN TRAVELING PROJECT SPECIALIST SPECIALIST SENIOR SPECIALIST CGINEERS IAI NIE[NANCE DOCUM4ENT HELHSPECIALIST FR ENGINEERS FOREMEN ENGINEERS CONTROL PHYSICS QUALITf CIONTRO PROTECTION SHIFT M4ECHIIC PLANT SPECIALIST SENIOR SPEC IAL IST so FOREMEN M ENGINEERS OFFPERVSO ISPECALIS FOROE FOREMEN EGERSSUPERVCSOR Cit041ISTRY SURVEILLANCE REGULATORY SENIOR OOST CONTROL SPECIALIST TRAINING SPECIALIST ALARA CONTROL INSTRUMENTATION S10RES RADIATION OPERAIOR AND CONTROL CONTROL AND RO FOREI1EN FOREMAN TEST FOREMEN TRAINING (D
AUXILIARY OPERATOR Unit #1 personnel are indicated for clarity only and are not a o
part of these specificatidns.
CONDUCT OF OPERATIONS CHART FIGURE 6.2-2
6.4 TRAINING 6.4.1 A retraining and replacement training progrm for the facility staff shall be maintained under the direction of the Training Supervisor and shall meet or ex coed the requirements and recomendations 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 Director - Nuclear Safety and QA and shall meet or exceed the requirements of Section 27 of the NFPA Code 1975, except that training sessions shall be conducted at least quarterly.
6.4-1 Amendment No. 46
6.5 REVIEW AND AUDIT Organizational units for the review and audic of plant operations shall be.constituted and have the responsibilities and authorities outlined below:
6.5.1 Plant Nuclear Safety Committee (?NSC) 6.5.1.1 Purpose As an effective means for regular review, evaluation, and main tenance of plant operational safety, a Plant Nuclear Safety Committee (FNSC) has been established.
The committee is chaired by the General Manager and composed of plant supervisory personnel.
6.5.1.2 Composition The P'lant Nuclear Safety Committee shall be composed of the follvwing, with a secretary to be named by the Chairman:
- a.
Chairman:
General Manager
- b.
Vice Chairman: Operations and Maintenance or Technical and Administrative Managers or Director-Nuclear Safety and QA
- c.
Engineering Supervisor
- d.
Maintenance Supervisor - Unit #2
- e.
Environmental and Radiation Control Supervisor
- f.
Quality Assurance Supervisor
- g.
Training Supervisor
- h.
Operating Supervisor - Unit #2
- i.
Administrative Supervisor -
Unit #2 6.5.1.3 Alternates Alternate members shall be appointed in writing by the PNSC Chairman to serve on a temporary basis; however, no more.than two alternates shall participate in PNSC activities as voting members at any one time.
6.5-1 Amendment No.
46
6.5.1.4 Coneultanta Consultants shall be utilized as determined by the PNSC Chairman to provide expert advice to the PNSC.
6.5.1.5 Meeting Frequency The PNSC shall meet at least once per calendar month and as convened by the PNSC Chairman.
6.5.1.6 Quorum A quoru of the FNSC shall consist of the Chairman or Vice Chairman plus three members including alternates.
6.5.1.7 Responsibilities
- a. Review of (1) all pro-adures required by Specif ica tion 6.8 and changes.aereto, (2) any other proposed procedures or changes :hereto as determined by the General Manager to affect nuclear safety.
- b.
Review of all proposed test and experiets that affect nuclear safety.
- c.
Review of all proposed changes to the Technical Specifitations.
- d.
Review of all proposed changes or modifications to plant systems or equipment.hat affect nuclear safety.
6.5-2 Amendment No. 46
- e.
Investigation of all violations of the Technical Specifi cations and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence to the Vice President -
Nuclear.Operations and to the Manager Corporate Nuclear Safety and Quality Assurance Audit.
- f.
Review of facility operations to detect potential safety hazards.
- g.
Performance of special reviews and investigations and reports thereon as requested by the Manager -
Corporate Nuclear Safety and Quality Assurance Audit.
- h.
Review of the Plant Security Plan and implementing procedures.
- i.
Review of the Emergency Plan and implementing procedures.
- j.
Review of all events requiring 24-hour reports to the NRC by regulations or Technical Specifications.
6.5.1.8 Authority
- a.
The Plant Nuclear Safety Committee shall be advisory.
- b.
The Plant Nuclear Safety Committee shall recommend to the General Manager approval or disapproval of proposals under 6.5.1.7.a. through d. above.
In the event of disagreement between the recommenda tions of the Plant Nuclear Safety Committee and the actions contemplated by the General Manager, the course determined by the General Manager to be more conserva tive will be followed with immediate notification to the Vice President - Nuclear Operations and to the Manager Corporate Nuclear Safety and Quality Assurance Audit.
6.5-3 Amendment No. 46
- c.
7he Plant Nuclear Saf.e;y C.mittee shal ae deter minations as to vbather or not proposals considered by
- he Comi::ee in=mv% lve unreviawed safet7 ques:tons.
This deterinati:n shall1 be subject to review by the 1.anage: - Corporate Nuclear Safet and Quality Assurance Audit as specified under 6.5.2.4.a.
6.5.1.9 Records Alnutes shall be kepe at the plant of all mee:ings of the ?lant Nuclear Safety Comittee and copims shall be sent to the Vice President - Nuclear Operations and to the Manager -
Corporate Nuclear Rafety anA Quality Assurance Audit.
6.5.1.10 ?:ocedures ri:an administra:ive procedures for committee opera:ion shal e
prepared and maiz:aIned.
6.5-4 Amendment No. 46
- 2.
Significant operating abnormalities or deviations from normal or expected performance of plant safety related struccures, systems, or components.
Review of events covered under this paragraph shall include the results of any investigations made and the recommendations resulting from such investigations to prevent or reduce the probability of recurrence of the event.
- e.
Any other matter involving safe operation of the nuclear power plant which the Manager - Corporate Nuclear Safety
& Quality Assurance Audit Section deems appropriate for.
considera:ion, or which is referred to the Manager Corporate Nuclear Safety I Quali:y Assurance Audi: Section by the onsite operating organization or by other functional organizational units within Carolina Power & Light Company.
Follow-uo Action 6.5.3.4 Resul:s of Corporace Nuclear Safety (CNS) reviews, including recamendations and concerns will be documented.
- a.
Copies of the documented review will be retained in the Corporate Nuclear Safety & Qual+/-:y Assurance Audit Section files.
SRecommena:ions and concesns will be submit:ed to :he Vice President Nuclear Generation within 14 days of determination.
Z.
A sumation of Corporate Nuclea: Safety recommendacions and concerns will be submitted to the President/Chief Executive 6.5-9 Amendment No. 46
Reports 6.5.4.3 Results of audit are approved by the Manager -
Corporate Nuclear Safety & Quality Assurance Audit Section and transmitted directly to the Company President/Chief Executive Officer, the Chief Operating Officer, as well as to the Executive Vice President Power Supply & Customer Services, the Senior Vice President -
Power Supply, and the Vice President -
Nuclear Safety & Research, and others as appropriate, within 30 days after the completion of the audit.
6.5.4.4 The corporate quality assurance audit program shall be conducted in accordance with written, approved procedures.
6.5.5 Fire Prevention and Loss Prevention 6.5.5.1 An independent fire protection and loss prevention inspection and audit shall be performed annually utilizing either qualified offsite personnel or an outside fire protection firm.
6.5.5.2 An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than three years.
6.5.12 Amendment No.
46
6.6 REPORTABLZ OCCURRENCE ACTION 6.6.1 The following actions shall be taken in the event of a reportable occurrence:
- a.
The Commission shall be notified and/or a report submitted pursuant to the requiremencs of Specification 6.9.
- b.
A copy of each Reportable Occurrence Report shall be forwarded to the Manager of Corporate Nuclear Safety and Quality Assurance Audit and the Vice President -
Nuclear Operations.
6.6-1 Amendment No.
46
6.7 SAMTET L.IMI VIOLATION 6.7.1 The folloving actions shall be taken in the event a Safet-7 Limit is violated:
- a.
The provisions of 10 CTR 50.36(c) (1) i) shall be complied vich iediatly.
- b.
The Safetry li-m+/-: violation shall be reported to the Commission, the Vice President - Nuclear Operations and the Manager of Corporate Nuclear Safecy and Quality Assurance Audit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- c.
A Sabety Li:
Violation Report shall be prepared.
The report shall be reviewed by the ?NSC.
This report shall describe (1) applicable circustances preceding the violation, (2) :he effec:s of the violation upon facility components, systems of structures, and (3) cor'rec:ve action taken to prevent recurrence.
- d.
The Sa.fety lim: VIolation Report shall be submci::ad to
- he Ccission, the Hanager of Corporate Nuclear Safety and Quality Assurance Audit and the Vice President - Nuclear Operations 14 days of the violation.
6.7-).
Amendment No. 46
6.8 PROCEURES 6.8.1 Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recomendations of Sections 5.1 and 5.3 of ANSI X18.7-1972 and Appendix "A" of USNRC Regulatory Guide 1.33 dated November 3, 1972, except as provided in 6.8.2 and 6.8.3 below.
6.8.2 Proposed operating procedures, overall plant operating proce duras, system descriptions, emergency procedures, fuel handling procedures, periodic test procedures, procedures for equipment maintenance which may affect nuclear safety, annunciator procedures, Fire Protection Program implementation procedures and any other procedures determined by the General Manager to affect nuclear safety, shall be reviewed by the PNSC and approved by the General Manager.
Prior to implementation, proposed changes to these procedures must also be reviewed and approved in this manner.
6.8.3 Temporary changes to procedures of 6.8.2 above may be made provided:
- a.
The intent of the original procedure is not altered.
- 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.
- c.
The change is docmented, reviewed by the PNSC and approved by the General Manager within three weeks of Implementation.
6.8-1 Amendment No.
46