ML14190A537
| ML14190A537 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 11/07/1979 |
| From: | Utley E CAROLINA POWER & LIGHT CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML14190A538 | List: |
| References | |
| GD-79-2848, NUDOCS 7911140209 | |
| Download: ML14190A537 (16) | |
Text
REGULA-U1NFORMATIUN DISTRIBUTION TEM (RIDS)
ACCESSION NBR;7911140209 0OCDATE: 79/11/07 NOTARIZED: YES DOCKET #
FACIL:S0-261 H. b, Robinson PlantVUnit 2, Carolina Power and Ligh 05000261 AUTH NAME AUTHOR AFFILIATION UTLEYE.E.
Carolina Power & Light Co, RECIPONAME
-RECIPIENT AFFILIATION SCHWENCER,A,.
Operating Reactors Branch 1
SUBJECT:
Requests amend to license DPR-23tchanging Tech Specs to reflect reorganization of Util Generation Dept.Class II fee encl.'
DISTR1BUTION CODE; A0015 COPIES RECEIVED:LTR ENCL SIZE:_
+
3 TITLE: Qeneral Distribution for after Issuance of Operating Lic N 0 T ES.
RECIPIENT COPIES RECIPIENT COPIES 10 CODE/NAME LITR ENCL 10 CODE/NAME LlTR ENGL ACTION:
05 BC5 OR 84 7
INTERNAL:
G F 1
1 02 NRC POR 1
1 12 I&E 2
2 14 TA/EO 1
1 i5 CORE PERF SR 1
1 17 ENGR BR I
1 18 REAC SFTY BR 1
1 19 PLANT SYS BR 1
i 20 EEB 1
1 21 EFLT TRTSYS 1
22 BRINKMAN 1
1 EPB 00R 1
1 OELD 1
0 EXTERNAL; 03 LPDR 1
1 04 NSIC 1
1 23 ACRS 16 16 nOV 151979 TOTAL NUMBER OF COPIES REQUIRED: LIR 39 ENCL 38
CP&L Carolina Power & Light Company November 7, 1979 FILE:
NG-3514(R)
SERIAL NO.:
GD-79-2848 Office of Nuclear Reactor Regulation Attention: Mr. Albert Schwencer, Chief Operating Reactors Branch No. 1 United States Nuclear Regulatory Commission Washington, D. C. 20555 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 LICENSE NO. DPR-23 REQUEST FOR LICENSE AMENDMENT -
CORPORATE REORGANIZATION
Dear Mr. Schwencer:
Effective November 3, 1979, Carolina Power & Light Company (CP&L) is reorganizing its Generation Department. The Generation Department is being split into two new departments, the Nuclear Operations Department and the Fossil Operations Department. Within the Nuclear Operations Department, the position of Manager of Nuclear Generation has been abolished. The plant manager positions at the Brunswick and Robinson Units have been elevated to the positon of General Manager and the new General Managers will report directly to the Vice President in charge of the Nuclear Operations Department. Also, the plant organization at the Robinson plant has been reorganized. The new organization is shown on the attached Figure 6.2-2.
The above changes necessitate changes in the.H. B. Robinson Unit 2 Technical Specifications. Accordingly, in accordance with the Code of Federal Regulations Title 10, Part 50.90 and Part 2.101, CP&L requests a revision to the Technical Specifications for H. B. Robinson to reflect the above reorganization.
Replacement pages for the Technical Specifications are enclosed. Changes are indicated by a vertical line in the right hand margin of the affected page.
411 Fayetteville Street
- P. 0. Box 1551
- Raleigh, N. C. 27602 7911140
Mr. Albert Schwencer
-2 In accordance with 10 CFR 170.12(c) we have determined that this revision constitutes one Class II Amendment. Accordingly, our check for $1,200 is enclosed.
If you have any questions on these items, please contact our staff.
Yours very truly, E. E. Utley Executive Vice President Power Supply & Customer Services EEU/jcb Enclosures Sworn to and subscribed before me this 7th day of November 1979.
No taryPb My Commission expires October 4, 1981.
cc: Mr. James P. O'Reilly (NRC)
OTfg PU L
I r
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 7911140
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 VtCE PRESIDENT NUCLEAR OPERATIONS CORPORATE NUCLEAR DEPARMENTSAFETY
& QUALITY STAFF j
ASSURANCE AUDIT MANAGER PLANT GEN. MANAGER PLANT NUCLEAR SAFETY COMMITTEE ADMINISTRATIVE ORGANIZATION OFF-SITE ORGANIZATION FOR
-LINES OF COMMUNICATION H.B. ROBINSON 2 MANAGEMENT FIGURE 6.2-I AND TECHNICAL SUPPORT 6.2-3
SRO-SENIOR REACTOR OPERATOR LICENSE GENERAL MANAGER RO REACTOR OPERATOR LICENSE ROBINSON PLANT MANAGER "MANAGER DIRECTOR OPERATION AND TECHNICAL AND NUCLEAR SAFETY MAINTENANCE ADMINISTRATIVE AND (.A.
SRO I _
OEATING MAINTENANCE O
nPERATIONS &
ENVIOMNA LT SUPERVISOR SUPERVISOR MAINTENANCE ENGINEERING ADMINISTRATIVE NVI RONMENTAL A
RAN SPECIALIST UNIT NO. 2 UNIT NO. 2 SUPERVISOR SUPERVISOR SUPERVISOR CONTROL SUPERVISOR SECURITY UNIT NO. I SUPERVISOR OPERATIONS TRAVELING PROJECT SPECIALIST SPECIALIST SENIOR SPECIALIST ENGINEERS HAINIENANCE DOCUMENT HEALTH SPECIALIST-FIRE FOREM4EN ENGINEERS CNTRO PHYSICS QUALITY CONT[ROL PROTECTION SHIFT MECHANIC PLANT SPECIALIST SENIOR SPECIALIST FOREMEN EGNRSOFFICE SPECIALIST SRO FOREMEN SUPERVISOR CHEMI STRY SURVEILLANCE REGULATORY SEN IOR COST CONTROL SPECIALIST TRAINING CNTROLE PERAO SPECIALIST ALARA RVISOF CONTROL INSTRUMENTATION STORES RADIATION OPERA:OR AND CONTROL CONTROL AND RO FOREMEN FOREMAN TEST FOREMEN TRAINING AUIXI LIARY PERATOR Unit #1 personnel are indicated for clarity only and are not a part of Lhese specificati5ns.
CONDUCT OF OPERATIONS CHART FIGURE 6.2-2
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Training Supervisor and shall meet or ex ceed the requirements and recommendations 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
6.5 REVIEW AND AUDIT Organizational units for the review and audit 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 (PNSC) has been established. The committee is chaired by the Plant Manager and composed of plant supervisory personnel.
6.5.1.2 Composition The Plant Nuclear Safety Committee shall be composed of the following, 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
- 1.
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
6.5.1.4 Consultants 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 quorum of the PNSC shall consist of the Chairman or Vice Chairman plus three members including alternates.
6.5.1.7 Responsibilities
- a.
Review of (1) all pro-idures required by Specifica tion 6.8 and changes.nereto, (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 experiments that affect nuclear safety.
- c.
Review of all proposed changes to the Technical Specifications.
- d.
Review of all proposed changes or modifications to plant systems or equipment.hat affect nuclear safety.
fK-.
- 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
- c.
The Plant Nuclear Safety Com.mi-ttee shall make deter minations as to whathzr or not proposals considered by
- he Commi:tee invoIve unreviewed safety questions.
This de:erminacizn shall be subject to review by the
.anager Corporate Nuclear Safet.
and Quality Assurance Audit as specified under 6.5.2.4.a.
R.9 Records Ainutes shall be kept at the plant of all meetings of the Plant Nuclear Safety Comittee and copies shall be sent to the Vice President - Nuclear Operations and to the Manager -
Corporate Nuclear qafety an Quality Assurance Audit.
.10 ?rocedures Wri.ten administrative procedures for committee opera:ion shall be pre;ared and =air:ained.
6.5-4
- 2. Significant opera:tng abnormalities or deviations from normal or expected performance of plant safety related structures, 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 consideration, or which is referred to the Manager Corporate Nuclear Safety & Quality Assurance Audit Section by the onsite operating organization or by other functional organizational units within Carolina Power.& Light Company.
Follow-up Action 6.5.3.4 Results of Corporate Nuclear Safety (CNS) reviews, including recommendations and concerns will be documented.
- a.
Copies of the documented review will be retained in the Corporate Nuclear Safety & Quality Assurance Audit Section files.
- b.
Recomendations and concerns will be submitted to the Vice President Nuclear Generation within 14 days of determination.
A summation of Corporate Nuclear Safety recommendations and concerns -will be submitted to the President/Chief Executive
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
6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken in the event of a reportable occurrence:
- a.
The Comission shall be notified and/or a report submitted pursuant to the requirements 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
6.7 SAE LMI VIOLATION 6.7.1 The follo-ing actions shall be taken in the event a Safety Limit is violated:
- a.
The provisions of 10 CR 50.36(c)(1)(i) shall be complied with immediately.
- b.
The Safety Limi: violation shall be reported to the Commission, the Vice President - Nuclear Operations and the Manager of Corporate Nuclear Safety 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 SafeCy Limi: Violation Report shall be prepared. The report shall be reviewed by the ?NSC. This report shall describe (1) applicable circumstances preceding the violation, (2) the effects of the violation upon facility components, systams of structures, and (3) corrective ac:ion taken to prevent recurrence.
4d. The Safety Limi: Violation Report shall be submitted to the Commission, the Manager of Corporate Nuclear Safety and Quality Assurance Audit and the Vice President - Nuclear Operations within 14 days of the violation.
6.7-1
6.8 PROCEDURES 6.8.1 Written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of Sections 5.1 and 5.3 of ANSI N18.7-1972 and Appendix "A" of USNRC Regulatory Guide 1.33 dated November 3, 1972, except as provided in 6.8.Z and 6.8.3 below.
6.8.2 Proposed operating procedures, overall plant operating proce dures, 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 documented, reviewed by the PNSC and approved by the General Manager within three weeks of implementation.
6.8-1