ML20077C618
| ML20077C618 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 05/06/1991 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077C619 | List: |
| References | |
| NUDOCS 9105220195 | |
| Download: ML20077C618 (11) | |
Text
_-
+$po use UNITED STATES
.E}se f,i NUCLE AR REGULATORY COMMISSION t,
j W ASHINGT ON, D. C. 20555
/
ENTERGY OPERATIONS, INC.
SYSTEM ENERGY RESOURCES, INC.
SOUTH MISSISSliJI ELECTRIC POWER ASSOCIATION MISSISSIPPI POWER AND LIGHT COMPANY DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION, UNIT 1 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No. 76 License No. NPF-29 1.
The Nuclear Regulatory Commission (the Corraission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated Merch 15, 1991, 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 1; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Consission; 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 conson 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 Cormission's regulations and all applicable requirements have been satisfied.
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. 2.
Accoroingly, 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 NPT-29 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Ensironmental Protection Plan contained in Appendix B as revised through An.endment No. 76, are hereby incorporated into this license. Entergy Operations, Inc. shall operate the f acility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION hvjeu g)?
h s c~)
Theodore R. Quay, Director Project Directorate IV-1 Division of Reactor Projects 111, IV, and V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
May 6,1991
ATTACHMENT TO LICENSE AMENDMENT NO. 76 FACILITY OPERATING LICENSE NO. NPF-29 000KET NO. 50-416, Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change, l
l REMOVE PACES INSERT PAGES 6.1 6.1 6.2 6.2 6.2a 6.2a 6.6 6.6 6.7 6.7 6.8 6.8 6.12 6.12 6.13 6.13
NL-90/06 6.0 AMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The General Manager, Plant Operations shall be responsible for overall I
unit operation and shall delegate in writing the succession to this responsi-bility during his absence.
6.1.2 The Shif t Superintendent or, during his absence from the Control Room, a designated individual shall be responsible for the Control Room command function.
A management directive to this effect signed by the Vice President, Operations GGNS shall be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION 6.2.1 GFFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit organization and corporate management, respectively.
The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
a.
Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions.
These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.
These requirements shall be documented in the UFSAR and updated at least annually, b.
The General Manager, Plant Operations shall be responsible for over-l all unit safe operation and shall have control over those oasite activities necessary for safe operation and maintenance of the plant.
c.
The Vice President, Operations GGNS shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
d.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures, 6.2.2 UNIT STAFF The unit organization shall be subject to the following; a.
Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.2-1.
b.
At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor.
In addition, while the reactor is in OPERATIONAL CONDITION 1, 2 or 3, at least one licensed Senior Reactor Operator shall be in the Control Room.
GRAND GULT-UNIT 1 6-1 Amendment No. 76
ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) c.
A health physics technician
- shall be onsite when fuel is in the reactor.
d.
All CORE ALTERATIONS shall be observed and 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 operation.
e.
A site Fire Brigade of at least 5 members shall be maintained onsite at all times *.
The Fire Brigade shall not include the Shift Superintendent, the STA, the two other members of the minimum shift crew necessary for safe shutdown of the unit, and any personnel required for other essential functions during a fire emergency.
At least one A0 shall be available to respond to non-fire-fighting commands from the Control Room.
f.
Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions; e.g., senior reactor operators, reactor operators, health physicists, auxiliary operators, and key maintenance personnel.
Adequate shift coverage shall be maintained without routine heavy use of overtime.
However, in the event that unforeseen problems require substantial amounts of overtime to be used, the following guidelines shall be followed:
1.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.
2.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven-day period, all excluding shift turnover time.
3.
A break of at least eight hours should be allowed between work periods, including shift turnover time.
4.
Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.
Any deviation from the above guidelines shall be authorized by the General Manager, Plant Operations or his designee, or higher levels i
of management, in accordance with estaolished procedures and with documentation of the basis for granting the deviation.
Controls shall be included in the procedures such that individual overtime shall be
- The number of health physics technicians and Fire Brigade personnel may be less than the minimum requirements 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 accommodate unexpected absence provided immediate action is taken to fill the required positions.
GRAND GULF-UNIT 1 6-2 Amendment No. 76
ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) reviewed monthly by the General Manager, Plant Operations, or his j
cesignee to assure that excessive hours have not been assigned.
Routine deviation from the above guidelines is not authorized.
g.
The Operations Superintendent, Shift Superintendents, Operations Assistants, and Shift Supervisors shall each hold a Senior Reactor Operator License, h.
The Manager Plant Operations must have been a Senior Reactor Operator or have been certified on a plant of this type.
6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)
FUNCTION 6.2.3.1 The ISEG shall function to examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of plant design and operating experience information, including plants of similar design, which may indicate areas for improving plant safety.
COMPOSITION 6.2.3.2 The ISEG shall be composed of a multi-disciplined dedicated, onsite, group with a minimum assigned complement of five engineers or appropriate specialists.
GRAND GULE-UNIT 1 6-2a Amendment No. 76
A NL-90/06 ADMINISTRATIVE CONTROLS INDEPENDENT SAFETY ENGINEERING GROUP (ISEG) (Continued)
RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of unit activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
AUTHORITY 6.2.3.4 The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities operations activities or other means of improving unit safety to the Vice President, Operations GGNS.
6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide technical support to the Shif t Superintendent in the areas of thermal hydraulics, reactor engineering and plant analysis with regard to safe operation of the unit.
6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANSI N18.1-1971 for comparable positions, except for the Superintendent,
- Radiation Control and Shift Technical Advisor, who shall meet or exceed the education and experience requirements of ANSI /ANS 3.1-1981 as endorsed by Regul-atory Guide 1.8, Revision 2, 1987, and licensed personnel who shall meet or exceed the criteria of the accredited license training program; and those members of the Independent Safety Engineering Group used for meeting the minimum comple-ment specified in Section 6.2.3.2, each of whom shall have a Bachelor of Science degree or be registered as a Professional Engineer and shall have at least two years experience in their field, at least one year of which experience shall be in the nuclear field.
6.4 TRAINING-6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager, Nuclear Training shall meet or exceed INPO accreditation criteria and 10 CFR Part 55, and shall include familiarization with relevant industry operational experience.
6.5 REVIEW AND AUDIT 6.5.1 PLANT SAFETY REVIEW COMMITTEE (PSRC)
FUNCTION 6.5.1.1 The PSRC shall function to advise the General Manager, Plant Operations j
on all matters related to nuclear safety.
"Not responsible for sign-off function.
GRAND GULF-UNIT 1 6-6 Amendment No. 76
l
. ADMINISTRATIVE CONTROLS PLANT SAFETY REVIEW COMMITTEE (PSRC) (Continued)
COMPOSITION
- 6. 5.1. 2 The PSRC shall be composed of nine members of GGNS onsite operating organization management at the Superintendent level or above.
ALTERNATES
- 6. 5.1. 3 All alternate members shall be appointed in writing by the General Manager, Plant Operations to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PSRC activities at any one time.
MEETING FREQUENCY 6.5.1.4 The PSRC shall meet at least once per calendar month and as convened by the PSRC Chairman or Vice Chairman.
QUORUM 6.5.1.5 The quorum of the PSRC necessary for the performance of the PSRC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or Vice Chairman and four members including alternates.
RESPONSIBILITIES 6.5.1.6 The PSRC shall be responsible for review of:
a.
Station administrative procedures and changes thereto.
b.
The safety evaluations for (1) procedures, (2) changes to procedures, equipment or systems, and (3) 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 and all programs required by Specification 6.8 and changes thereto, c.
Proposed procedures and changes to procedures, equipment or systems which may involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
d.
Proposed tests or experiments which may involve an unreviewed safety question as defined in Section 50.59, 10 CFR, e.
Proposed changes to Technical Specifications or the Operating License.
GRAND GULF-UNIT 1 6-7 Amendment No. 76
e
- i..-
~
. ADMINISTRATIVE CONTROLS l
RESPONSIBILITIES (Continued) f.
Reports of violations of codes, regulations, orders, Technical Specifications, or Operating License requirements having nuclear safety significance or reports of abnormal degradation of systems designed i
to contain radioactive material, g.
Reports of significant operating abnormalities or deviatione 7
normal and expected performance of-plant equipment that affe.:,1uclear safety.
h.
Review of all REPORTABLE EVENTS.
i i.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components.
j.
The plant Security Plan and changes thereto.
L The Emergency Plan and char:ges thereto.
Items which may constitute a potential nuclear safety hazard as identified during review of facility operations.
m.
Investigations or analyses of special subjects as requested by the Chairman of the Safety Review Committee.
n.
Changes to the PROCESS CONTROL. PROGRAM, 0FFSITE DOSE CALCULATION MANUAL, and raasaste systems.
AUTHORITY 6.5.1,7 The PSRC shall:
a.
Recommend in writing to the General Manager, Plant Operations approval j-or disapproval of items considered under 6.5.1.6 a, c, d, e, j, and k,
- above, b.
Render determinations in writing to the General Manager, Plant Opera-l tions with regard to whether or not each item considered under i
6.5.1.6.a, c and d, above, constitutes 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 SRC of disagreement between the PSRC and the General Manager, Plant Operations; however, the General Manager, Plant Operations shall have responsibility for i
resolution of such disagreements pursuant to 6.1.1 above.
8 RECORDS
- 6. 5.1. 8 The PSRC shall maintain written minutes of each PSRC meeting that, at a minimum, document the results of all PSRC activities performed under the responsibility and authority provisions of these Technical Specifications.
Copies shall be provided to the SRC.
GRAND GULF-UNIT 1 6-8 Amendment No. 76
ADMINIS1PATIVE CONTROLS AUTHORITY
- 6. 5. 2. 9 The SRC shall report to and advice the Vice President, Operations GGNS on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.
RECORDS 6.5.2.10 Records of SRC activities shall be prepared, approved and distributed as indicated below:
a.
Minutes of each SRC meeting shall be prepared, approved and forwarded to the Vice President, Operations GGNS within 14 days following each 4
meeting.
b.
Reports of reviews encompassea by Section 6.5.2.7 above, shall be l
prepared, approved and forwarded to the Vice President, Operations GGNS within 14 days following completion of the review, i
c.
Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Vice President, Operations GGNS and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.
6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.3.1 Activities which affect nuclear safety shall be conducted as follows:
Procedures required by Technical Specification 6.8 and other proce-a.
dures which affect plant nuclear safety, and changes thereto, shall be prepared, reviewed and approved.
Each such procedure or procedure change shall be reviewed by an individual / group other than the individual / group which prepared the procedure or procedure change, but who may be from the same organization as the individual / group which prepared the procedure or procedure change.
Procedures other than Administrative Procedures shall be approved as delineated in writing by the General Manager, Plant Operations.
The General l
Manager, Plant Operations shall approve administrative procedures, i
security implementing procedures and emergency plant implementing procedures.
Temporary approval to procedures which clearly do not change the intent of the approved procedures may be made by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License.
Temporary changes shall be reviewed by the reviewing authority within 14 days of being issued.
For changes to procedures which may involve a change in intent of the approved procedures, the person authorized above to approve the procedure shall approve the change.
b.
Proposed changes or modifications to plant nuclear safety-related structures, systems and components shall be reviewed as designated by the Vice President, Operations GGNS.
Each such modification shall be reviewed by an individual / group other than the individual / group which designed the modification, but who may be from the same organization as the individual / group which designed the modifications.
Implementation of proposed modifications to plant nuclear safety-related structures, systems and components shall be approved by the General Manager, Plant Operations.
GRAND GULF-UNIT 1 6-12 Amendment No. 76.
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- NL-90/06 ADMINISTRATIVE CONTROLS ACTIVITIES (Continued)
Proposed tests and experiments which affect plant nuclear safety and c.
are not addressed in the final Safety Analysis Report shall be reviewed by an individual / group other than the individ*e '/ group which prepared the proposed test or experiment.
d.
Events reportable pursuant to Section 50.73 to 10 CFR Part 50 shall be investigated and a report prepared which evaluates the event and which provides recommendations to prevent recur enie.
Such report shall be approved by the General Manager, Plant Operations.
l e.
Individuals responsible for reviews performed in accordance with
- 0. 5. 3.1. a. 6. 5. 3.1. b, 6. 5. 3.1. c and 6. 5. 3.1. d shall meet or exceed the qualification requirements of Section 4.4 of ANSI 18.1, 1971, as previously designated by the Vice President, Operations GGNS or General Manager, Plant Operations, as applicable.
Each such review
(
shall include a determination of whether or not additional, cross-i disciplinary review is necessary.
If deemed necessary, such review shall be performed by the review personnel of the appropriate discipline, f.
Ear.h review shall include a determination of whether or not an unreviewed safety question is involved.
g.
Records Of.he above activities shall be provided to the General Manager, Plant Operations, PSRC and/or as necessary for required i
rev e.ii.
6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Comrission shall be notified pursuant to the requirements of Section 50.72 to 10 CFR Part 50, and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the PSRC and submitted to the SRC and the Vice President, Operations GGNS.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour.
The Vice President, Operations GGNS and the SRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the PSRC.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects'of the violation upon unit components, systems or structures, and (3) corrective actions ta6en to prevent recurrence.
GRAND GULF-UNIT 1 6-13 Amendment No. 76
-