ML20141G167
| ML20141G167 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 04/10/1986 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20141G172 | List: |
| References | |
| TAC-60158, NUDOCS 8604230309 | |
| Download: ML20141G167 (14) | |
Text
6 l
8 UNITED STATES E
j NUCLEAR REGULATORY COMMISSION vi
- y E
W ASHINGTON. D. C. 20655
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I MISSISSIPPI POWER & LIGHT COMPANY MIDDLE SOUTH ENERGY, INC.
SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No.10 License No. NPF-29 1.
The Nuclear Regulatory Commission (the Conunission) has found that:
I A.
The application for amendment to the Grand Gulf Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-29 filed by the Mississippi Power & Light Company acting for itself, Middle South Energy, Inc., and South Mississippi Electric Power Association (the licensees), dated November 14, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the 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 set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; E.
The issuance of this license amendment is in accordance with 10 CFR Part 51 of the Conunission's regulations and all applicable requirements have been satisfled.
2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment and paragra'phs 2.C(2) and 2.C.(28) of Facil.ity Operating License No. NPF-29 are hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through 8604230309 860410 PDR ADOCK 05000416 P
Amendment No.10 and the Environmental Protection Plan contaired in Appendix B are hereby incorporated into this license. Mississippi Power & Light Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(28) Advisor to Vice President MP&L shall have on its nuclear operations staff, one or more corporate management officials or advisors (who may be either permanent employees or contracted consultants) who have substantial commercial nuclear power plant operating management experience and who will advise on all decisions affecting safe operation of the plant. This requirement shall be in effect until the plant has accumulated at least 6 months at power levels above 90% of full power.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing
Enclosure:
Technical Specifications Changes Date of Issuance: APS
- Lif o
ATTACHMENT TO LICENSE AMENDMENT NO.10 FACILITY OPERATING LICENSE NO. NPF-29
^
DOCKET N0. 50-416 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 areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
Amended Overleaf
,P_ age Page a
6-1 6-2 6-3 6-6 6-5 6-9 6-10 6-11 6-12 6-13 6-14 D
m
6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The GGNS General Manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
~
6.1.2 The Shift 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, Nuclear Operations shall be reissued to all station personnel on an annual basis.
6.2 ORGANIZATION 6.2.1 0FFSITE The offsite organization for unit management and technical support shall be as shown on Figure 6.2.1-1.
6.2.2 UNIT STAFF The unit organization shall be as shown on Figure 6.2.2-1 and:
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.
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 Shif t 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.
- 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 6-1 Amendment No. 10 l
ADMINISTRATIVE CONTROLS
~
l UNIT STAFF (Continued) i f.
' Administrative procedures shall be developed and implemented to limit i
the working hours' of unit staf f 'who perform safety-related functions; I
e'.g.,
senior reactor operators, reactor operators, health physicists, l
auxiliary operators, and key ma'intenance 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:
l 1.
An individu..I 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 /> l
straight, excluding shift turnover time.
l l
2.
An individual should not be permitted to work more than 16 hout s i
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 l
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 j
excluding shift turnover time.
3.
A break of at least eight hours should be allowed between work i
periods, including shift turnover time.
4.
Except during extended shutdown periods, the use of overtime i
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 GGNS General Manager or his designee, or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.
Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the GGNS General Manager or his designee to assure that excessive hours have not been assigned.
Routine deviation from the above guide-lines is not authorized.
6.2.3 INDEPENDENT SAFEfY 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 GULF-UNIT 1 6-2 l
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l TABLE 6.2.2-1 l
MINIMUM SHIFT CREW COMPOSITION l
POSI' TION NUMBER OF INOLVIOUALS REQUIRED TO FILL POSITION l.
CONDITIONS 1, 2, & 3 CONDITIONS 4 & 5 SS 1
1 Sh0 1
None R0 2
1 la 2
1 STA
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1 None TABLE NOTATION SS - Shift Superintendent with a Senior Reactor Operators License on Unit 1.
SRO - Individual with a Senior Reactor Operators License on Unit 1.
R0 - Individual with a Reactor Operators License or. Unit 1.
AO - Auxiliary Operator.
STA - Shift Technical Advisor.
4 Except for the Shift Superintendent, the Shift Crew Composition may be one less than the minimum requirements of Table 6.2.2-1 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 of onduty shift crew members provided immediate actio'n is taken to restore the Shift Crew Composition to within the minimum requirements of Table 6.2.2-1.
This provision does not permit any shif t crew position to be unmanned upon shif t change due to an oncoming shift crewman being late or absent.
During any absence of the Shift Superintendent from the Control Room while the unit is in OPERATIONAL CONDITION 1, 2 or 3 an individual, other than the Shif t Technical Advisor, with a valid SR0 license shall be designated to assume the Control Room command function.
During any absence of the Shift Superintendent from the Control Room while the unit is in OPERATIONAL CONDITION 4 or 5, an l
individual with a valid SRO or R0 license shall be designated to assume the Control Room command function.
e
~~~
~ ~ ~ ~ ~
- l GRAND GULF-UNIT 1 6-5 l
-- - - l - - - - - -
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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 error,s 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, Nuclear Operations.
l 6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide technical support to the Shift 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 qualifications of ANSI N18.1-1971 for comparable positions and the supplemental requirements specified in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter # to all licensees, except for the Chemistry / Radiation Control Super-intendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975; the Shift Technical Advisor who shall meet or exceed the qualifications referred to in Section 2.2.1.b of Enclosure I of the October 30, 1979 NRC letter to all operating nuclear power plants; and those members of the Independent Safety Engineering Group used for meeting the minimum complement 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 Training Superintendent, shall meet or exceed the requirements and recommendations of Section '5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55 and the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter # to all licensees, and snall 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 GGNS General Manager on all matters related to nuclear safety.
ANot responsible for sign-off function.
- Except that the experience and other training information provided in the Ifcensee's letter to the NRC dated July 29, 1985 are acceptable for the individuals listed in that letter.
GRAND GULF-UNIT 1 6-6 Amendment No. 10 l
ADMINISTRATIVE CONTROLS 6.5.2 SAFETY REVIEW COMMITTEE (SRC)
FUNCTION 6.5.2.1 The SRC shall function to provide independent review and audit of designated' activities in the areas of:
a.
nuclear power plant operations b.
nuclear engineering c.
chemistry and radiochemistry d.
metallurgy e.
instrumentation and control f.
radiological safety g.
mechanical and electrical engineering h.
quality assurance practices i
COMPOSITION 6.5.2.2 The SRC shall be composed of the:
l Chairman:
Vice President, '.uclear Operations Member:
Vice President, Nuclear Engineering & Support Member:
Director, Nuclear Plant Engineering l
Member:
Site Director, GGNS Member:
Director, Quality Assurance Member:
Designated Representative, Middle South Services, Inc.
Member:
GGNS General Manager Member:
Ofrector, Nuclear Licensing and Safety Member:
Manager, Radiological and Environmental Services Member:
Principal Engineer, Operations Analysis g
Two or more additional voting members shall be consultants to Mississippi Power and Light Company consistent with the recommendations of the Advisory i
Committee on Reactor Safeguards letter, Mark to Palladino dated October 20, 1981.
The SRC members shall hold a Bachelor's degree in an engineering or physical science field or equivalent experience and a minimum of five years of technical experience of which a minimum of three years shall be in one or more of the disciplines of 6.5.2.la through h.
In the aggregate, the membership of the committee shall provide specific practical experience in the majority of the disciplines of 6.5.2.la through h.
ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SRC activities at any one time.
1 GRAND GULF-UNIT 1
~6-9 Amendment No.10
ADMINISTRATIVE CONTROLS i
CONSULTANTS 6.5.2.4 Consultants, in addition to those required in Specification 6.5.2.2, shall be utilized as determined by the SRC Chairman to provide expert advice to the SRC.
No more than three consultants shall participate as voting members in SRC activities at any one time.
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MEETING FREQUENCY 6.5.2.5 The SRC shall meet at least once 'er calendar quarter during the initial year of unit operation following fuel loaoing and at least once per six months thereafter.
QUORUM 6.5.2.6 The quorum of the SRC necessary for the performance of the SRC review and audit functions of these Technical Specifications shall consist of the Chairman or his designated alternate and at least 7 SRC voting members including l
alternates.
No more than a minority of the quorum shall have line responsibility for operation of the unit.
REVIEW 6.5.2.7 The SRC shall review:
a.
The safety evaluations for (1) changes to procedures, equipment 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.
c.
Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
d.
Proposed changes to Appendix A Technical Specifications or this Operating License.
e.
Violations of codes, regulations, orders, Technical Specifications, ifcense requirements, or of internal procedures or instructions having 3
nuclear safety significance.
f.
Significant operating abnormalities or deviations from normal and l
expected performance of unit equipment that affect nuclear safety.
g.
All REPORTABLE EVENTS.
h.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components 4
j that could affect nuclear safety.
i l
1.
Reports and meetings minutes of the PSRC.
1 j.
Written reports from audits of the ALARA program.
2 GRAND GULF-UNIT 1 6-10 Amendment No.10 l
OP
ADMINISTRATIVE CONTROLS AUDITS 6.5.2.8 Audits of unit activities shall be performed under the cognizance of the SRC.
These audits shall encompass:
a.
The conformance of unit operat.fon to provisions contained within the Appendix A Technical Specifications and applicable' license conditions at least once per 12 months.
b.
The performance, training and qualifications of the entire unit staff at least once per 12 months.
The results of actions taken to correct deficiencies occurring in c.
unit 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 mcnths.
The Emergency Plan and implement *ng procedures at least once per e.
12 months.
f.
The Security Plan and implementing procedures at least once per 12 months.
g.
Any other area of unit operation considered appropriate by the SRC or the Vice President, Nuclear Operations.
l h.
The Fire Protection Program and implementing procedures at least once per 24 months.
i.
An independent fire protection and loss prevention inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm.
j.
An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant et intervals no greater than 36 months.
k.
The radiological environmental monitoring program and the results thereof at least once per 12 months.
1.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.
m.
The PROCESS CONTROL PROGRAM and implementing procedures for sdlidification of radioactive wastes at least once per 24 months.
n.
The performance of activities required by the Quality Assurance Program to meet the criteria of Regulatory Guide 4.15, February 1979, at least once per 12 months.
GRAND GULF-UNIT 1 6-11 Amendment No.10 l
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ADMINISTRATIVE CONTROLS l
l AUTHORITY 1
i 6.5.2.9 The SRC 'shall report to and advise the Vice President, Nuclear l
Operations on those areas of responsibility specified in Sections 6.5.2.7 and 6.5.2.8.
l l
RECORDS 6.5.2.10 Records of SRC activities shall be prepared, approved and distributed as indicated below:
Minutes of each SRC meeting shall be prepared, approved and forwarded a.
to the Vice President, Nuclear Operations within 14 days following l
each meeting.
b.
Reports of reviews encompassed by Section 6.5.2.7 above, shall be prepared, approved and forwarded to the Vice President, Nuclear l
Operations within 14 days following completion of the review.
c.
Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the Vice President, Nuclear Operations and to the l
management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.
I 6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES l
6.5.3.1 Activities which affect nuclear safety shall be conducted as follows:
a.
Procedures reouired by Technical Specification 6.8 and other proce-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 l
than Administrative Procedures shall be approved as delineated in writing by the GGNS General Manager.
The GGNS General Manager shall approve administrative procedures, 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.
l b.
Proposed changes or modifications to plant nuclear safety-related l
structures, systems and components shall be reviewed as designated l
by the Site Ofrector, GGNS.
Each'such modification shall be reviewed l
l 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.
Impirmentation of proposed modifications to plant nuclear safety-related structures, systems and components shall be approved by the GGNS General Manager, j
GRAND GULF-UNIT 1 6-12 Amendment No.10 l t
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l
ADMINISTRATIVE CONTROLS l
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 individual / 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 recurrence.
Such report shall be approved by the GGNS General Manager.
Individuals responsible for reviews performed in accordance with e.
6.5.3.1.a, 6.5.3.1.b, 6.5.3.1.c and 6.5.3.1.d shall meet or exceed l
the qualification requirements of Section 4.4 of ANSI 18.1, 1971, as previously designated by the Site Director, GGNS or GGNS General Manager, as applicable.
Each such review shall include a determina-tion of whether or not additional, cross-disciplinary review is necessary.
If deemed necessary, such review shall be performed by j
the review personnel of the appropriate discipline.
I f.
Each review shall include a determination of whether or not an unreviewed safety question is involved.
g.
Records of the above activities shall be provided to the GGNS General Manager, PSRC and/or as necessary for required reviews.
6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
The Commission shall be notified pursuant to the requirements of a.
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, Nuclear Operations.
l 6.7 SAFETY LIMIT VIOLATION i
6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
The NRC Operations Center shall be notified by telephone as soon as a.
possible and in all cases within one hour.
The Vice President, Nuclear Operations 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) appifcable circumstances precedin0 the violation, (2) effects of the violation upon unit components, systems or structures, and (3) corrective action taken to prevent recurrence.
o GRAND GULF-UNIT 1 6-13 Amendment No. 10 l
ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued) c.
The Safety Limit Violation Report shall be submitted to the Commission, the SRC and the Vice President, Nuclear Operations within l
14 days of the violation.
d.
Critical operation of the unit ~shall not be resumed until authorized by the Commission.
6.8 PROCEDURES AND PROGRAMS 3
6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
The applicable procedures recommended in Appendix "A" of Regulatory a.
Guide 1.33, Revision 2, February 1978.
b.
Refueling operations.
c.
Surveillance and test activities of safety related equipment.
I d.
Security Plan implementation.
e.
Emergency Plan implementation.
f.
Fire Protection Program implementation.
g.
PROCESS CONTROL PROGRAM implementation.
h.
OFFSITE DOSE CALCULATION MANUAL implementation.
i.
Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 4.15, February 1979.
6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed as required by 6.5, above, prior to implementation and shall be reviewed periodically as set forth in cdministrative procedures.
6.8.3 The following programs shall be established, implemented, and maintained:
a.
Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.
The systems include the:
1 1.
RCIC system outside containment containing steam or water, I
except the drain line to the main condenser.
l 2.
RPR system outside containment containing steam or water, except the line to the LRW system and headers that are isolated by manual valves.
3' HPCS system.
4.
LPCS system.
5.
Hydrogen analyzers of the combustible gas control system.
1 GRAND GULF-UNIT 1 6-14 Amendment No.10 l
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