ML20011D654
| ML20011D654 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 12/14/1989 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20011D655 | List: |
| References | |
| NUDOCS 8912280176 | |
| Download: ML20011D654 (28) | |
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"g UNITED STATES j
NUCLEAR REGULATORY COMMISSION n
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WASHINGTON, D. C. 20555 3
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SYSTEM ENERGY. RESOURCES, INC.. et al.
l DOCKET k0. 50-416 GRAND GULF NUCLEAR. STATION. UNIT 1 -
AMENDMENT TO FACILITY 0PERATING LICENSE 1
Amendment No. 65 License No. NPF-29 1.
The Nuclear Regulatory Comission (the Comission) has found that A.
The application for amenoment by System Energy Resources, Inc.,
(thelicensee),datedAugust 15, 1989, as supplemented by letters dated August 22, September 22, September 27 (two letters), October 27, October 30, November 21, and November 30, 1989, complies with the i
standards and requirements of the Atomic Energy Act of 1954, as i
amended (the Act), and the Comission'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 regulattuns 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have j
been satisfied.
l 8912280176 891214 DR ADOCK 05000 L
-2_
2.
Accordingly, the license is amended by changes to the license conditions, Technical Specifications, and Environmental Protection Plan as t
indicated in the attachment to this license amendment.
3.
This license amendment is effective as of its date of issuance.
The license conditions shall be implemented within 180 days of date of issuance and upon the officiel transfer of responsibilities between System Energy Resources, Inc. and Entergy Operations, Inc.
FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By:
Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachments:
Changes to the License Conditions.
Technical Specifications, and Environmental Protection Plan Date of Issuance: December 14, 1989 i
SEE PREVIOUS CONCURRENCES-DFC :LA:PDZl:DRPR:PM:PDZl:DRPR: *bGC
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NAME : PAnderson.: LKintner:
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DATE.:.
- 12/13/89
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0FFICIAL RECORD COPY
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i ATTACWMENT.TO LICENSE. AMENDMENT N0. 65 FACILITY.0PERATING LICENSE.NO..NPF.29 00CKET.NO. 50 416 i
l-l Replace the following pages of the Operating License and its attachments and Appendices with the attached pages.
The revised pages are identified by Amenament number and contain vertical lines indicating the area of change.
Remove Insert License No. NPF-29:
License No. NPF-29:
-2 through 17, inclusive 1 through 17, inclusive Attachnent 1: :
i 18 18 : :
Title Page Title Page Apperdix A:
Appendix A:
6-9 6-9 Appendix B:
Appendix B:
Title Page Title Page 4-2 4-2 Appendix C:
Appendix C:
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1 2
4 4
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~g UNITED STATES NUCLEAR REGULATORY COMMISSION n
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WASHINGTON, D. C. 205S5
'59.....g ENTERGY OPERATIONS. INC.
t SYSTEM. ENERGY RESOURCES..INC.
SOUTH MISS!SSIPPI ELECTRIC POWER. ASSOCIATION MISSISSIPPI. POWER.& LIGHT COMPANY DOCKET NO. 50-416 GRAND. GULF NUCLEAR STATION, UNIT 1 FACILITY OPERATING LICENSE License No. NPF-29 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for license filed by Mississippi Power & Light Company (NP&L), for itself and Middle South Energy Inc., (now-renamed System Energy Resources, Inc. (SERI)) and South Mississippi ElectricPowerAssociation(SMEPA),asamended,(hereinafterreferred i
to as the licensees) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made; B.
Construction of the Grand Gulf Nuclear Station, Unit 1 (the facility),
has been substantially completed in conformity with Construction Permit No. CPPR-118 and the application, as amended, the provisions of the Act, and the regulations of the Comission; C.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the i
Comission (except as exempted from compliance in Section 2.D. below);
D.
There is reasonable assurance:
(1)thattheactivitiesauthorized by this operating license can be conducted without endangering.the health and safety of the public; and (ii) that such activities will-be conducted in compliance with the Comission's regulations set 1 orth in 10 CFR Cha Section 2.0. below)pter I- (except as exempted f rom compliance in
- i I
1 Amendment No. 65
o 3
E.
Entergy Operations, Inc. (E01), is technically qualified to engage in the activities authorized by this operating license in accordance with the Commission's regulations set forth in 10 CFR Chapter I; F.
The licensees have satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; G.
The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public; H.
Af ter weighing the environmental, economic, technical, and other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of Facility Operating License No. NPF-29, subject to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix B, is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and I.
The receipt, possession, and use of source, by-product and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40, and 70.
2.
Based on the foregoing findings regarding this facility and pursuant to Commission Order CLI-84-19, dated October 25, 1984, License NPF-13, as amended, is superseded by this Facility Operating License NPF-29 which is hereby issued to Entergy Operations, Inc., Mississippi Power & Light l
Company, System Energy Resources, Inc., and South Mississippi Electric Power Association to read as follows:
A.
This license applies to the Grand Gulf Nuclear Station (GGNS), Unit l
1, a boiling water nuclear reactor and associated equipment (the facility), owned by System Energy Resources, Inc., and South Mississippi Electric Power Association and operated by Entergy Operations, Inc.
F.
The f acility is located in Claiborne County, Mississippi, and 1s-described in the licensees' " Final Safety Analysis Report," as supplemented and amended, and in the licensees' Environmental Report, as supplemented and amended.
B.
Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:
(1) Entergy Operations, Inc. (E01) pursuant to Section 103 of the l
Act and 10 CFR Part 50, to possess, use, and operate the facility at the designated location in Claiborne County, Mississippi, in accordance with the procedures and limitations set forth in this license; (2) System Energy Resources, Inc., and South Mississippi Electric Power Association to possess, but not operate, the facility at the designated location in Claiborne County, Mississippi, in accordance with the procedures and limitations set forth in this l
license; 2
Amendment No. 65 L
4 (3) E01, pursuant to the Act and 10 CFR Part 70, to receive, possess 1
and use at any time at the facility site and as designated solely for the facility special nuclear material as reactor fuel, in 1
accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4) E01, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radia-tion monitoring equipment calibration, and as fission detectors in amounts as required;-
(5) E01, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to
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receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) E01, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
(7) (a) SERI is authorized to transfer up to 15 percent of its 90.0 percent ownership share in Grand Gulf Nuclear Station, Unit 1 (GGNS Unit 1), to certain equity investors identified in the submissions of October 31, 1988 and November 11, 1988, and at the same time to lease back from such purchasers such interest sold in the facility. The term of.
the lease is for approximately 26 years subject to a right of renewal. Such sale and lease back transactions are subject to the condition that lessors and anyone else who may acquire an interest under these transactions are prohibited from exercising directly or indirectly any control over (1) GGNS Unit 1, (ii) power or energy produced by GGNS Unit 1, or (iii) the licensees of GGNS Unit 1.
Further any rights acquired under this authorization nay be exerc,ised only in compliance with and subject to the requirements and restrictions of this operating license, the Atomic Energy Act of 1954, as amended, and the Consnission's regulations.
For purposes of this condition, the limitations of 10 CFR'50.81, as now in effect and as they may be subsequently amended, are fully applicable to the lessors and any successors in interest to those lessors, as long as the license of GGNS Unit I remains in.effect.
3 Amendment No. 65
6 (b) SERI is required to notify the NRC in writing prior to any change in (1) the terms or conditions of any new or existing sale or lease agreements executed as part of the above author-ized financial transactions, (ii) the GGNS Unit 1 operating agreement, (iii) the existing property insurance coverage for GGNS Unit I that would materially alter the representations and conditions set forth in the staff's Safety Evaluation Report dated December 19, 1988 attached to Amendment No. 54.
In addi-tion, SERI is required to notify the NRC of any action by a lessor or other successor in interest to SERI that may have an effect on the operation of the facility.
C.
The license shall be deemed to contain and is subject to the condi-tions specified in the Comission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or here-after in effect; and is subject to the additional conditions specified-or. incorporated below:
(1) Maximum Power Level E01 is authorized to operate the' facility at reactor core power l levels not in excess of 3833 megawatts thermal (100 percent power) in accordance with the conditions specified herein.
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
are hereby incorporated into this license.
Entergy Operations, Inc. shall operate the l
f acility in accordance with the Technical Specifications.and the Environmental Protection Plan.
4 Amendment No. 65
,O _
(3) Antitrust Conditions (a) MP&L and SERI shall comply with the antitrust conditions I
delineated in Appendix C.
SERI is authorized to transfer its rights to possess, to use and to operate the facility to E01, provided however, that until further authorization of the Commission, MP&L and SERI shall continue to be responsible for compliance with the obligations imposed 1
on the licensees in these antitrust conditions, and provided further that EDI accepts the right to possess, use and-operate the facility and SERI accepts-the right to possess the facility subject to the outcome of the pending separate antitrust review of the antitrust considerations related to the application dated September 2, 1986.
SERI is authorized to-transfer its rights to operate the facility to E01.
?
(b) MP&L and SERI are responsible and accountable for the
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actions of their respective agents to the extent said agent's actions contravene the antitrust conditions in Appendix C.
(4)
Independent Verification of Staff Performance and Other Plant.
Activities (Section 13.4, SER, 55ER #2)
(a) MP&L* shall establish a subcommittee of the Corporate Safety {
Review Conunittee to review ano evaluate the:
(i) Status and readiness of the plant and systems needed to support intended modes of operation and/or testing; (ii) Readiness of personnel to conduct intended operation and testing; L
(iii) Morale and attitudes of plant personnel that have a i
bearing on safe plant operation; i
l (iv) Past performance in plant operations and adherence to procedures and administrative controls; (v) Changes in current organization with regard to experience and qualifications of plant management and-supervisory personnel since the last evaluation; (vi) Results and effectiveness of the Plant Safety Review Committee (PSRC),
(vii) Status of plant as compared to other BWR startups based on the subconanittee's knowledge and experience.
5 Amendment No. 65
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Reviews shall be conducted prior to exceeding 50 percent of full power and within 30 days following comaletion of the 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> warranty run. The subcomittee small be com-posed of a minimum of three professionals not employees of a
MP&L, with experience which will be responsive to the I
concerns presented above.
In conducting these evaluations, the subcomittee shall conduct interviews of representa-4 tives of all levels of plant staff management.
The subcomittee shall report directly to the Chairman of the Corporate Safety Review Comittee and, in turn, MP&L shall submit the report of these reviews to NRC.
s (b) The Plant Safety Review Committee shall review all Unit 1 preoperational testing and system demonstration activities performed concurrently with the Unit 1 Startup Test Program to assure that the activity will not affect the safe performance of the portion of the Unit 1 Startup Program being performed.
The review shall address, as a minimum, system interaction, span of control, staffing, procedures, security and. health physics, with respect to performance of the activities concurrent with the i,
portion of the Unit 1 Startup Program being performed.
(5) Deferred Preoperational Deficiencies MP&L shall satisfactorily resolve those deficiencies which were I
deferred from the preoperational testing program on a schedule that shall assure that the capability of a system required to be operaole by Technical Specification is not degraded.
(6) Soil Structure Interaction (Section 3.7.1, SER, SSER #2)
Prior to startup following the first refueling outage, MP&L shall l-complete structural modifications, if required, as a result of the NRC staff's completion of its review of MP&L* responses.
(7) Seismic Instrumentation (Section 3.7.4, SER, SSER #2)
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Prior to startup (ollowing the first refueling outage, the installa-tion of triaxial strong motion accelerometers.on reactor supports shall be completed.
(8) Masonry Walls-(Section 3.8.3, SER, SSER #2)
Prior to startup following the first refueling outage, MP&L shall l
complete structural modifications, if required, as a result of the a
NRC staff's completion of its review of the MP&L response to IE' I
- The original license authorized Mississippi Power & Light Company (MP&L) to operate _the facility. Amendment 27 authorized SERI to operate the facility.
Consequently, there are certain historical references to MP&L and SERI, in.
their past roles as operators of the facility, in this license.
i.
6 Amendment No. 65
i (9) DynamicTesting(Section3.9.2,SER,SSER#2,SSER#4,SSER#5)
MP&L shall conduct vibrational neasurement and inspection programs l
during preoperational and initial startup testing in accordance with the guidelines _ of Regulatory Guide 1.20 " Comprehensive Vibration Assessnent Program for Reactor Internals During Preoperational and Initial Startup Testing," for prototype reactors. An evaluation report demonstrating satisfactory results shall be provided to the NRC for review and approval no later than 6 months after completion of the startup test program.
(10)DynamicQualification-(3.10,SER,SSER#1,SSER#2,SSER#4,SSER#5)
(a) Prior to startup following the first refueling outage, MP&L shall l complete any modifications or replacement of equipment found necessary as a result of the fatigue evaluation.
In the interim, MP&L shall document the occurrence of every safety
.l relief valve actuation into the suppression pool; the' associated cumulative damage factors shall be calculated for typical representative equipment and kept up-to-date; and E01 shall l
report to NRC any malfunction of equipment that occurs due to any safety relief valve discharge.
(b) MP&L shall perform an in-situ test of the High Pressure Core l
Spray (liPCS) service water pump and evaluate.the effects of flow induced vibration on the HPCS service water pump.
This evaluation shall be provided to the NRC for review and approval.
Prior to startup following the first refueling outage, MP&L shall complete all modifications as a result of the NRC staff's review of the test results and evaluation.
(c) Prior to actual use in fuel handling operations, MP&L shall l
qualify the fuel-handling and auxiliary platform, in-vessel L
l rack, and storage container for defective fuel.
l (11) Environmental Qualification (Section 3.11, SER; SSER #1; Appendix H, SSER F2; 55ER 45)
Prior to March 31, 1985, HP&L shall environmentally. qualify all electrical equipment as required by 10 CFR 50.49.
(12)SurveillanceofControlBlade(Section4.2.3.14,SER)
Within 30 days after plant startup following the first refueling outage, SERI shall comply with items 1, 2 and 3 of Bulletin' No. 79-26 3
and submit a written response to NRC on item 3.
l 4
(13) Core Stability Analysis and Prohibition of Natural Circulation (Section 4.4.1, 5ER)
(a) Prior to startup following the first refueling outage, MP&L l
shall submit a new core stability analysf.s for operation i
beyond cycle 1.
7 Amendment No. 65 i
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(b) Natural circulation shall be prohibited as an operating mode.
(14) Loose Parts Monitoring (Section 4.4.1, SER)
Prior to startup following the first refueling outage, MP&L shall l
submit an evaluation of the loose parts monitoring system to address conformance to Regulatory Guide 1.133, Revision 1, dated May 1981.
(15)ScramDischargeVolume(Section4.6,SER) incorporate the following additional modifications into the scram
' h Prior to startup following the first refueling outage, MP&L shall discharge volume system:
(1) Redundant vent and drain valves, and (ii) Diverse and redundant scram instrumentation for each instrumented volume, including both delta pressure sensors and float sensors.
(16)ContainmentPurge(Section6.2.4,SSER#5)
Prior to startup following the first refueling outage, MP&L shall l
provide for NRC review a reevaluation of the need to use the contain-ment purge mode of the containment cooling system.
This study should include, but is not limited to, data gathered during the first fuel cycle related to airborr.e activity level (ALARA), overall containment air quality and personnel access to containment.
Based on the above cited study, EDI shall propose the purge criteria to be used for the l
remainder of the plant life.
(17) Containment Pressure Boundary (Section 6.2.8, SER)
Prior to startup following the first refueling outage, MP&L shall l
replace the feedwater check valve disc with a disc made from a suitable material.
(18) Pressure Interlocks on Valves Interfacing at Low and High Pressure (Section 6.3.4, 55ER #2)
Prior to startup following the first refueling outage, MP&L l
shall implement isolation protection against overpressurization of the low pressure emergen:y core cooling systems (RHR/LPCI.ana LPCS) at the high and low pressure interface containing a check valve and a closed motor-operated valve.
i e
d 8
Amendment No. 65
(19) IE Information Notice 79-22. Qualification of Control System (Section 7.8.C. SER, 55ER #2)
Prior to startup following the first refueling outage, MP&L shall l
complete any design changes found necessary as a result of this review.
(20) S_tandby Service Water System (Section 9.2.1 SER, SSER #2)
(Deleted)
(21) Spent Fuel Pool Ventilation System (Section 9.4.2 SER,.SSER #2)
If spent irradiated fuel is placed in the spent fuel pool prior to installation and operability of the safety related backup fuel pool cooling pump room coolers, the plant shall be placed in shutdown condition and remain shut down with the RHR system dedicated to the fuel pool cooling mode.
(22) Remote Shutdown Panel (Section 9.5.4.1, SER,'SSER #2)
Prict to startup following the first refueling outage, MP&L shall l
install electrical isolation switches between the control room and the Division 1 remote shutdown panel.
l (23) Fire Protection Program (Section 9.5.9, SER)
E01 shall maintain in effect and fully implement all provisions of -
l the approved Fire Protection Plan.
In addition, E01 shall maintain-the fire protecti,on program to meet the intent of Appendix R to 10 CFR Part 50, except that an oil collection system for the reactor coolant pump is not required.
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9 Amendment No. 65
i (24) Interplant Communication Systems (Section 9.6.1.2, SER, SSER #2, SSER
- 4, 55ER 75)
Tests of the communication systems used to mitigate the consequences of an event and attain a safe plant shutdown shall be completed during preoperational and startup tests. An evaluation of the test results shall be provided for NRC review within 90 days after test completion. Any system modifications found necessary as a result of NRC review shall be completed prior to startup following the first refueling outage.
(25) Reliability of Diesel-Generators (Sections 8.3.1, 9.6.3 through 9.6.7, SER, 55ER #2, 55ER f4, 55ER #6)
(a) Prior to startup following the first refueling outage, a heavy duty turbocharger gear drive assembly shall be installed on all EMD diesel-generators.
(b) E01 shall comply with TDI emergency diesel generator requirements l specified in Attachment 2 to this. license.
(26) Turbine Disc Integrity (Section 10.2.1, SER, SSER #1)
E01 shall ultrasonically inspect the bores and keyways of the low l
pressure turbine discs for indications of cracking prior to exceeding 50,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of operation. All unacceptable indications and their dispositions shall be reported prior to startup for the next cycle of l
operation. These inspections shall continue on a 50,000 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> interval until the pctential'for turbine disc cracking has been assessed and.
an acceptable alternate inspection scheoule has been established.
1 (27) Circulating Water System (Section 10.4.5, SER)
EDI shall not fill the Unit 2 circulating water system (including l
the natural draft cooling tower basin) until Unit I flooding concerns related to this system are resolved to the satisfaction of the.NRC staff.
(28) Advisor to the Vice President MP&L shall have on its nuclear operations staff, one or more corporate l nanagement 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 cf the plant.
This requirement shall be in effect until the plant has accumulated at l
least 6 months at power levels above 90' percent of full power.
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l 10 Amendment No. 65
(29)OperatingShiftAdvisor(Section13.1.2,SER)
At least one individual on each operating shift shall have substantive previous BWR operatin0 experience, including startup and shutdown of a BWR and under conditions that one might expect to encounter during the initial startup and power escalation at Grand Gulf plant. This individual is not required to be licensed on Grand Gulf Unit I and need not be a MP&L employee, but as a minimum shall be retained on a l
contract basis to act as a consultant or advisor to the GGNS shift Such an experienced person shall be assigned to each operating crew.
shift until the plant achieves and demonstrates full-power operation.
(30) Training Instructors (Section 13.2, SER)
[ DELETED]
(31)InitialTestProgram(Section14,SER) j MP&L shall conduct the post-fuel-loading initial test program (set forth in Section 14 of the Final Safety Analysis Report, as amended) without making any major modifications of this program unless such
)
modifications have been identified and have received prior NRC approval. Major mooifications are defined as:
)
(a) Elimination of any test identified in Section 14 of the Final l
]
Safety Analysis Report, as amended, as being essential; (b) Modification of test objectives, methods or acceptance criteria i
for any test identified in Section 14 of the Final Safety l
1 Analysis Report, as amended, as being essential; l
(c) Performan:;e of any test at a power level different from that i
described in the program; and l
(d) Failure to complete any tests included in the described program (planned or scheduled for power levels up to the authorized powerlevel).
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11 Amendment No. 65
(32)PartialFeedwaterHeating(Section15.1,SER,SSER#2)
Operation of the plant in the partial feedwater heating mode for the purpose of extending the normal fuel cycle shall be prohibited until analyses which justify that operation are provided to and approved by the NRC staff.
(33)NUREG-0737 Conditions (Section22.2)
The following conditions shall be completed to the satisfaction of l
the NRC. These conditions reference the appropriate items in Section 22.2, "TMI Action Plan Requirements for Applicants for Operating Licenses," in the Saf ety Evaluation Report and Supplements 1, 2, 3, 4, and 5 to NUREG-0831.
(a) Centrol Room Design Review (I.D.1, SER; Appendix E, SSER #2, ISER #4, 55ER #5)
Prior to startup following the first refueling outage, SERI shall demonstrate the ability to maintain an " effective temperature" condition of 85'F or less in the remote shutdown panel (RSP) room for at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> with an ambient outdoor temperature of at least 95'F.
(b) TrainingDuringLow-PowerTesting(I.G.1,SER)
Prior to restart following the first refueling outage, MP&L shall (
complete the additional training and testing related to THI Action Plan I.G.1 as described in Section 2.3 of the MP&L' submittal dated April 3,1986.
(c) Post Accident Sampling (II.B.3, SER, SSER #1, SSER #4, SSER #5)
Prior to startup following the first refueling outage, MP&L shall l incorporate the additional requirements into the procedure for 1
relating radionuclide gaseous and ionic species to estimate core damage as discussed in Section II.B.3.1 of SSER #4.
(d) Hydrogen Control (Section II.B.7, SER, SSER #2, SSER #3, 55ERf4,55ER#5)
(1) During the first cycle of operation, MP&L shall maintain a suitable program of analysis and testing of the installed hydrogen ignition system.
EDI shall submit to the NRC l
quarterly reports on the status of their research programs.
l 12 Amendment No. 65
(a) E01 shall amend its research program on hydregen control I
measures to include, but not be limited to, the following items:
(1) Perform containment sensitivity analysis to determine the adequacy of the hydrogen control system for a spectrum of degraded core accidents including the determination of accident sequences for which equip-nent survivability is assured; (2) Research to investigate the conditions leading to and consequences resulting from hydrogen combustion in the wetwell and containment.
Testing shall be performed in a larger scale facility such as-the ore-quarter scale test f acility proposed by MP&L; (3) Research to investigate the conditions' leading to and consequences resulting from hydrogen combustion in the drywell; (4) Confirmatory tests on thermal response of selected equipment exposed to hydrogen burns.
(b) E01 shall perform feasibility studies.to examine the l
options for enhancing equipment survivability for essential equipment located in the vicinity of the suppression pool or other regions subjected to severe environments.
The options to be studied in such feasibility studies shall include thermal shielding, additional cooling, and relocation of essential equipment.
(2)
(a) E01 shall complete its research program on hydrogen control l I
to show that the hydrogen control system will perform its intended-function in a manner that provides adequate safety l
margins. This research program shall be completed on a schedule which reflects the requirements of 10 CFR 50.44.
(b) If it is determined that plant modifications are required l
to obtain NRC approval that an aaequate hydrogen control system for Grand Gulf is installed, then these modifications shall be completed on a schedule which is approved by the NRC.
(e)
Instrumentation for Detection of Inadequate Core Cooling (II.F.2, SER, SSER 62)
MP&L shall submit a report addressing the analysis performed by the l
BWR Owners' Group regarding additional instrumentation relative to inadequate core cooling and shall implement the staff's requirements after the completion of the staff's review of this report.
These modifications shall be completed on a schedule acceptable to the staff.
13 Amendment No. 65
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)
(f) Modification of Automatic Depressurization System Logic-Feastb111ty f or Increased Diversity for Some Event Sequences JII.K.3.18, 5ER, 55ER #2, 55ER #4)
Prior to startup following the first refueling outage, MP&L shall l i
provide, for NRC review, justification for the timer delay set-tings, revisions to the emergency procedures cover.ing the use of the manual inhibit switch, proposed Technical Specification sur-veillance procedures for the timer and switch, and shall imple-ment alternative logic modification (Option 4) of the automatic i
depressurization system.
(g) QualificationofADSAccumulators(II.K.3.28,SSER#5)
Priortostartupfollowingthefirstrefuelingoutage,MP&Lshalll perform an integrated leak test on the ADS air system, perform-sampling to establish instrument air quality, provide instrumen-tation to monitor ADS air receiver pressure, establish suitable surveillance procedures for the ADS air system and provide pro-posed changes to the Technical Specifications associated with the surveillance procedures.
3 (34) SRV Test Program (Section A-39, Appendix C, SER, SSER #1, SSER #2)
During Cycle 1, an inplant SRV test program shall'be carried out to confirm that the containment building response to SRV loads is acceptable. Results of these tests shall be provided to NRC no later than four months after test-completion.
l 1
(35) Post-LOCA Vacuum Breaker Position Indicators Prior to startup following the first refueling outage, MP&L shall l
install position indicators with redundant indication and alarm in the control room for the check valves associated with the drywell post-LOCA vacuum breakers.
(36) Emergency Response Facilities (Generic Letter 82-33, NUREG-0737 Supplement 1, 55ER #5)
E01 shall complete the emergency response capabilities, as required by Attachment 1.
(37) Evaluation of Licensee's Technical Specification Problem Sheets (Section 16.3, 55ER #6) l Prior to startup following the first refueling outage, MP&L shall l
l implement the following modifications:
1 l
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l-s 14 Amendment No. 65 i
(a) Include an emergency override of the test mode of the Division 3 HPCS diesel generator to permit response to emergency signals and to return the control of the ciesel generator to the emergency standby mode.
(Item No. 333. TS 4.8.1.1.2.d.12.b)
(b) Provide the second level undervoltage protection for Division 3 power supply (Item No. 373, TS Table 3.3.3-2).
(c) Incorporate a bypass or coincident logic in all Division 1 and 4
2 diesel generator protective trips, except for trips on diesel engine overspeed ano generator differential current (Item No.
808. TS 4.8.1.1.2.d.16.d).
(38) Control Room Leak Rate (Section 6.2.6. SSER f6)
E01 shall operate Grand Gulf Unit I with an allowable control room l
leak rate not to axceed 590 cfm.
Upon restart of construction of Unit 2 control room, E01 will be-permitted to operate at a leak rate l
of 760 cfm as evaluated in SSER No. 6.
(39) Temporary Secondary containment Boundary Change For a period of time not to exceed 144 cumulative hours, the provi-sions of Specification 3/4.6.6.1 may be applied to the ra11roed bay area including the exterior railroad bay door on the auxiliary building in lieu of the present secondary containment boundaries that isolate the railroad bay area. While the railroad bay area is being used as a secondary containment boundary, the railroad bay door may be opened fur the purpose of moving trucks in and out provided the four hour limitation in ACTION a of Technical Specification 3.6.6.1 is reduced to one hour. A fire watch shall be established in the railroad bay area while the door is being used as a secondary containment boundary.
(40) Temporary Ultimate Heat Sink Change With the plant-in OPERATIONAL condition 4, SSW cooling tower basin A may be considered OPERABLE in accordance with Technical Specification 3.7.1.3 with less than a 30 day supply of water (without makeup) during the time that SSW basin B is drained to replace its associated service water pump provided:
(a) SSW basin A water level is maintained greater than or equal.to l
87".
(b) At least two sources of water (other than normal makeup with one source not dependent on offsite power) are available for makeup to SSW basin A.
This license condition inay remain in effect until plant startup following the outage scheduled for fall 1985.
15 Amendment No. 65
D.
The facility required exemptions from certain requirements of Appendices A and J to 10 CFR Part 50 and from certain requirements of 10 CFR Part 100.
These include:
(a) exemption from General Design Criterion 17 of Appendix A until startup following the first refueling outage, for (1) the emergency override of the test mode for the Division 3 diesel engine, (2) the second level undervoltage protection for the Division 3 diesel engine, and (3) the generator ground over current trip function for the Division 1 and 2 diesel generators (Section 8.3.1 of SSER #7) and (b) exemption from the requirements of Paragraph III.D.2(b)(11) of Appendix J for the containment airlock testing following normal door opening when containment integrity is not required (Section 6.2.6 of SSER #7).
These exemptions are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest.
In addition, by exemption dated December 20, 1986, the Commission exempted licensees from 10 CFR 100.11(a)(1), insof ar as it incorporates the definition of exclusion area in 10 CFR 100.3(a), until April 30, 1987 regarding demonstration of authority to control all activities within the exclusion area (safety evaluation accompanying Amendment No. 27 to License (NPF-29).
This exemption is authorized by law, and will not present an undue risk to the public health and safety, and is consistent with the coninon defense and security.
In addition, special circumstances have been found justifying the exemption.
Therefore, these exemptions are hereby granted pursuant to 10 CFR 50.12. With the granting of these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act and the rules and regulations of the Comission.
C.
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training ana qualifi-cation, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and-27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:
" Grand Gulf Nuclear Station Physical' Security Plan," with revisions submitted through September 1, 1987; " Grand Gulf Nuclear Station Guard Training and Qualification Plan," with revisions submitted through March 10, 1987; and
" Grand Gulf Nuclear Station Safeguards Contingency Plan," with revisions submitted through August 25, 1987.
Changes made in accordance with 10 CFR 73.55 shall be implemented in accoraance with the schedule set-forth therein.
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l 16 Amendment No. 65-
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F.
E01 shall report any violations of the re::drements contained in I
Section 2, items C.(1), C.(4) thro' ugh C.(38) of this license within twenty-four (24) hours.
Initial notification shall be made in accordance with the provisions of 10 CFR 50.72 with written follow-up in accordance with the procedures described in 10 CFR 50.73(b), (c),
and (e).
G.
The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance,ith Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
H.
This license is effective as of the date of issuance and shall expire at midnight on June 16, 2022.
FOR-THE NUCLEAR REGULATORY C0KMISSION f
0
% k/
.arold R. Denton, Director
' Office of Nuclear Reactor Regulation Attachments:
1.
Attachments 1 and 2 2.
Appendix A - Technical l
Specifications (NUREG-0934) 3.
Appendix B - Environmental Protection Plan 4
Appendix C - Antitrust Conditions Date of Issuance: November 1, 1984 17 Amendment No. 65
E01 shall complete the following requirements on the schedule noted below:
0 Emeroency Response facilities (Generic Letter 82-33. NbREG-0737 Supplement 1, 55ER #5 E01 shall implement the specific items below, in the manner described in l
MP&L letter (AECM-83/0232) dated April 15, 1983, as modified in MP&L letter (AECM-83/0486) dated August 22, 1983, no later than the following specified dates:
(a) Safety Purameter Display System (SPDS)
(1) Submit a safety analysis and implementation July 1985 plan to the NRC (2) SPDS fully operational and operator trained Prior to startup following first refueling outage.
(b) Detaileo Control Room Design Review (DCRDR)
(1) Submit a program plan to the NRC December 1984 (2) Submit a summary report to the NRC including July 1986 a proposed schedule for implementation (c) Regulatory Guide 1.97 - Application to Emergency Response Facilities (1) Submit a report to the NRC describing how the February 1985 l
requirements of Supplement 1 to HUREG-0737 i
have been or will be met.
(2)
Implement (installatien or upgrade)
Prior to startup requirements of R.G. 1.97 with exception following first l
of flux monitoring ano coolant level monitoring.
refueling outage.
l (3)
Implement'(installation or upgrace)
Prior to startup l
requirements of R.G.1.97 for coolant level 1ollowing second
{
i monitoring.
refueling outage.
{
(4)
Implement (installation or upgrade)
Prior to startup I
reouirements of R.G. 1.97 for flux monitoring.
following fourth refueling outage.
l (d) Uperace Emergency Operating Procedures (E0P's)
(1) Submit a Procedures Generation Package to the April 1985 NRC.
18 Amendment No. 65 i
Transamerica Delavri Inc. (TDI) Diesel Generator Maintenance and Surveillance Requirements (NUREG-1216, August 1986) 1.
Maintenance and Surveillance Program E01shallimplementandmaintainineffecttheprovisionsofthemaintenance\\
and surveillance program for the TDI emergency diesel generators at GGNS Unit 1 as identified in the MP&L letter dated July 18, 1986-(AECM-86/0172) and as approved in the staff's Safety Evaluation Report attached to the NRC letter dated December 9, 1986, subject to the provisions of paragraphs 2 and 3 below.
2.
Changes i
E01 may make changes to the approved maintenance and surveillance program without prior approval of the Commission provided the changes do not adverse-ly affect the operability or reliability of the diesel generators or involve changes in the Phase 1 Surveillance requirements of paragraph 3 below or otherwise change license conditions or Technical Specifications or result in an unreviewed safety question as defined in 10 CFR 50.59.
E01 l
shall maintain in auditable form, a current record of all such changes, including an analysis.of the effects of the change on diesel generator operability and reliability, and shall make such records available to NRC inspectors upon request.
All changes to the program shall be reported annually to the Director of the Office of Nuclear Reactor Regulation, along with the FSAR revisions required by 10 CFR 50.71(e).
3.
Phase 1 Component Surveillance Requirements E01 shall comply with the following requirements:
(
3.1 Connecting Rods Connecting rod assemblies shall be subjected to the following inspections at each major engine overhaul *:
The surfaces of the rack teeth shall be inspected for signs of a.
l fretting.
If fretting has occurred, it shall be subject to an j
engineering evaluation for appropriate corrective action.
- The frequency of the major engine overhauls referred to in these requirements shall be consistent with Section IV.1. " Overhaul Frequency" in Revision 2 of Appendix II of the Design Review / Quality Revalidation report which was I
transmitted by MP&L letter dated July 18, 1986.
1 Amendment No. 65 l
o ADMINISTRATIVE CONTROLS i
6.5.2 SAFETY REVIEW COMMITTEE (SRC) 2 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 COMPOSITION 6.5.2.2 The SRC shall be composed of a Chairman and nine voting members.
Two or more additional voting members shall be consultants to Entergy Operations, Inc., consistent with the recommendations of the Advisory Committee on Reactor Safeguards letter, Mark to Palladino dated October 20, 1981.
The Chairman and members shall meet the qualifications below.
The SRC Chairman shall hold a Bachelor's degree in an engineering or
. physical science field or an equivalent and a minimum-of six years of professional level managerial experience in the power field.
In addition, the Chairman shall have the necessary overall nuclear background to determine when to call consultants and contractors for dealing with complex problems beyond the scope of Entergy Operations, Inc., expertise.
l 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.
GRAND GULF-UNIT 1 6-9 Amendment No. 65
APPENDIX B TO FACILITY LICENSE NO. NPF-E9 GRAf0 GULF NUCLEAR STATION UNIT 1 ENTERGY OPERATIONS. INC.
j-DOCKET NO. 50-416 ENVIRONMENTAL PROTECTION PLAN OCT0EER 1984 I
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Amendment No. 65
by the aerial surveys, and walking patrols will be directed to the problem areas to evaluate the extent of the problem to be corrected, t
The Erosion Control Inspection Program shall begin upon commencement of normal transmission line inspection procedures. Semi-annual surveys shall continue until stabilization of soil and vegetation (i.e., ground cover establishment) is achieved.
A summary of the field inspection program and any procedures implemented to control abnormal erosion conditions associated with transmission line mainten-ante activities shall be reported in the Annual Environmental Operation Report in acccrdance with Subsection 5.4.1.
Field logs indicating locations of erosion damage and measures taken to rectify erosion problem areas and estimation of the time to achieve efisetive stabilization will be maintained and available for inspection for a period of five years.
Results reported shall contain infor-mation encompassing but not limited to inspection date, estimated size of erosion problem area, probable cause of erosion, type of stabilization program, and date of effective stabilization, as appropriate.
4.2.2 C_oolino Tower Drift Program Seven samplirg sites will be utilized to measure cooling tower crift-deposition, i
At least two of the sampling sites will have duplicate sampling devices.
Six of the seven sites will be located in areas where maximum salt deposition is predicted. These areas were extrapolated from the Bechtel Salt Deposition Model developed for the GGNS Final Environmental Report. The seventh sampling site l
will be a control site located south of Raymond, Mississippi.
Fallout samples will be collected using buckets with a known volume of deionized water in each.
The buckets will be located four to six feet above the ground, I
fitted with bird rings, and covered with fine mesh screens to exclude leaves and insects.
The samples will be collected on a quarterly basis and analyzed for calcium, magnesium, sodium, iron, phosphates, nitrates, chloride, fluorides, sulfates, and total dissolved solics.
These parameters were selected because past analyses have shown them to be prevalent in the cooling water source water.
The results of these analyses will be correlated with local rainfall data and 4-2 Amendment No. 65
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i APPENDIX C ANTITRUST CONDITIONS OPERATING LICEN5E NO. NFF-29 i
MP&L and SERI (the term licensees in Appendix C refers to NP&L and SERI) shall l
comply with the following antitrust conditions:
i I.
DEFINITIONS (a) " Western Mississippi Area" means the counties of: Walthall, Lawrence, Jefferson Davis, Covington, Simpson, Smith, Scott, Leake, Attala, Choctaw, Montgomery, Grenaca Yalobusha, Panola, Tate, DeSoto, Pike, Amite, Wilkinson, Adams, Franklin, Lincoln, Copiah, Jefferson, i
Claiborne, Hinds, Rankin, Madison, Yazoo, Warren, Issaquena, Sharkey.
Humphreys. Holnes, Carroll, Leflore, Sunflower Washington, Bolivar, Tallahatchie, Quitman, Coahoma, and Tunica. An entity shall be deemed to be in the " Western N1ssissippi Area" if'it has electric power generation, transmission, or distribution facilities located in whole or in part in the above described area.
(b) " Bulk Power" means the electric power, and any attendant energy, supplied or made available at transmission or subtransmission voltage by one entity to another, j
(c) " Entity" means a person, a private or public corporation, a munici-pality, a cooperative, an association, a joint stock association or business trust owning, operating or proposing to own or operate i
equipment or f acilities for the generation, transmission or distribu-tion of electricity, providea that, except for municipalities or rural electric cooperatives, " entity" is restricted to those which are or will be public utilities under the laws of the state in which the entity transacts or will transact business or under the Federal Power Act, and are or will be providing electric service under a contract or rate schedule on file with and subject to the regulation of a state regulatory commission or the Federal Power Commission.
(d) " Cost" means any operating and maintenance expenses involved together with any ownership costs which are reasonably allocable to the transaction consistent with power pooling practices (whereapplicable).
No value shall be included for loss of revenues f rom sale of power at wholesale or retail by one party to a customer which another party might otherwise serve.
Cost shall include a reasonable return on Licensees' investment.
The sale of a portion of the capacity of a generating unit shall be upon the basis of a rate that will recover to the seller the pro rata part of the fixed costs and operating and maintenance 1
Amendment No. 65
2 expenses of the unit, provided that, in circumstances in which licensees and one or more entities in the Western Mississippi I
Area take undivided interest in a unit in fee, construction costs ana creration and maintenance expenses shall be paid pro rata.
i II.
INTERCONNECTIONS (a) Licensees shall interconnect with and coordinate reserves by means of the sale and purchase of emer bulk puwer with any entity (ies) gency and/or scheduled maintenance in the Western Mississippi Area engaging in or proposing to engage in electric bulk power supply on terms that will provide for Licensees' costs in connection therewith and allow the other party (fes) full access to the benefits of reserve coordination.
(b) Emergency service and/or scheduled maintenance service to be provided i
by each party shall be furnished to the fullest extent available from the supplying party and desired by the party in need.
Licensees and each party (ies) shall provide to the other emergency service and/or scheduled maintenance service if and when available from its own generation and from generation of others to the extent it can do so without impairing service to its customers incluaing other electric systems to whom it has firm consnitments.
(c) Licensees and the other party (1es) to a reserve sharing arrangement shall from time to time jointly establish the minimum reserves to be installed and/or 'provided under contractual arrangements as necessary to maintain in total a reserve margin sufficient to provice adequate reliability of power supply to the interconnected systems of the parties.
If Licensees plan their reserve margin on a pooled basis i
l with other Entergy Corporation companies, the reserves jointly l
established hereunder shall be on the same basis.
Unless otherwise agreed upon, minimum reserves shall be calculated as a percentage of estimated peak load responsibility.
No party to the arrangerrent shall be required to maintain greater reserves than the percentage of its estimated peak load responsibility which results from the aforesaid calculation, provided that, if the reserve requirements of Licensees are increaseo over the amount Licensees would be required to maintain without such interconnection, then the other party (ies) shall be required to carry or provide for as its ttheir) reserves the full amount in kilowatts or such increase.
1 (d) The parties to such a reserve sharing arrangement shall provide such amounts of ready reserve capacity as may be adequate to avoid the imposition of unreasonable I
2 Amendment No. 65
~
1 (b)
In the event that during the term of the instant license, or any extension or renewal thereof, licensees obtain participation in the ownership of or rights to a portion of the output of one or more nuclear generating units constructed, owned and operated by any affiliate or subsiciary of the Entergy Corporation l
i other than licensees or by any successor in title to the Grand
)
GulfNuclearUnits,licenseesshallexerttheirbesteffortsto obtain participation in such nuclear unit (s) by any entity (ies) in the Western Mississippi Area requesting such participation on t
terms no less favorable than the terms of licenseos' participa-tion therein.
V.
TRANSMISSION SERVICES (a) Licensees shall facilitate the exchange of bulk power by trans-mission over its transmission facilities between or among two or more entities in the Western Mississippi Area with which it is interconnected; and between any such entity (ies) and any such l
entity (ies) engaging in bulk power supply outside the Western Mississippi Area between whose facilities Licensees' transmission lines and other transmission lines would form a continuous electrical path, provided that (1) permission to utilize such othertransmissionlineshasbeenobtained,and(2)thearrange-ments reasonably can be accommodated from a functional and tech-nical standpoint. Such transmission shall be on terms that fully compensate Licensees for their cost. Any entity (ies) recuesting such transmission arrangements shall give reasonable l
advance notice of its (their) schedule and requirements.
foregoing applies to any entity (ies) to which Licensees may(The be interconnected in the future as well as those to which they are nowinterconnected.)
(b) Licensees shall include in their planning and construction pro-gram sufficient transmission capacity as required for the trans-actions referred to in subperagraph (a) of this paragraph, providedthatanyentity(ies)intheWesternMississippiArea give Licensees sufficient advance notice as may be necessary to accommodate its (their) requirements from a functional and tech-nical standpoint and that such entity (ies) fully compensates Licensees for their cost.
Licensees shall not be required to construct transmission facilities which will be of no demonstrable present or future beriefit to Licensees.
V1. p0WER FOR RESALE i
Licensees will sell power for resale to any entity (ies) in the Western Mississippi Area now engaging in or proposing to engage in retail distribution of electric power.
4 Amendment No. 65
_. _ _