ML19332D143

Proposed Tech Specs,Establishing New Company Called EOI as sys-wide Nuclear Operating Company

ML19332D143
Person / Time
Site:	Grand Gulf
Issue date:	11/21/1989
From:	SYSTEM ENERGY RESOURCES, INC.
To:
Shared Package
ML19332D141	List: AECM-89-0191, Provides Further Clarification to 890815 Application for Amend to License NPF-29.Addl Info Approved by Plant Safety Review Committee ML19332D143
References
NUDOCS 8911300069
Download: ML19332D143 (33)

Text

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s Attcchment 4 to AECM-89/0191 P g3,1-i.

c PCOL-89/07 GRAND GULF UNIT 1 OPERATING LICENSE' MARKUP s

8911300069 891121 PDR ADOCK 05000416 P

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-1 fNTYMGY 0AntMIons Tat:.

SSISSIPPI POWER & LIGHT COMPANY SYSTEP ENERGY RESOURCES. INC.

. SOUTH MISSIS $1PPI ELECTRIC POWER ASSOCIATION 4

DOCKET N0. 50-416 1

GRAND GULF NUCLEAR STATION. UNIT 1 FACILITY OPERATING LICENSE License No. NPF-29 1.

The Nuclear Regulatory Comission (the Commission or the NRC) has found that:

A.

The application for license filed by Mississippi Power & Light Company (MP&L), for itself and Middle South Energy. Inc., (now renamed System Energy Resources, Inc._($iRI)? and South-Mississippi Electric Power Associatior,

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:: th: 'S::::::) complies with the standards and require-ments-of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have n

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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,

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the provisions of the Act, and the regulations of the Comission; C.

.The facility will operate in confomity with the application, as-amended, the provisions of the Act, and.the regulations of the Commission (except as exempted from compliance in Section.2.0.

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 forth in 10 CfR Chapter I (except as exempted from compliance in Section 2 D below);

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to engage in the activities authorized by this operating license in accordance with the Commission's regulations set forth in

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10 CFR Chapter I;

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Amendment No. 27, l

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The ' licensees have satisfied the applicable provisions of 10 CFR Part:140,L" Financial Protection Requirements and Indemnity Agreements," of the Comission's regulations;

.G.-

The. issuance of this license will not be inimical to the comon defense and security or to the health and safety of the public; H.

After 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 p,rotection of the environment set forth in the Environmental Protection Plan attached as Appendix B, is in accordance with-10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied; and v

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 Comission's regulations in 10 CFR Parts 30, 40, and 70.

2.

Based on the foregoing findings regarding this facility and pursuant to Comission 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 Mississippi Power 8 Light Company, EdW)y L c.

System Energy Resources Inc., and South Mississippi Electric Power s

Association to read as follows:

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s A.

This license-applies to the Grand Gulf Nuclear Station (MNS),

Unit 1, a boiling water nuclear en etor and associated equipment (the facility), owned by.Systcm Energy Resources, Inc., and South Mississippi Electric Power Association and operated by SyM =

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5:r;; t = r n:, :::. The facility is located in Claiborne

. County, Mississippi, and is described in the licensees" Final

. Safety Analysis Report, as. supplemented and' amended, and in the u

l-licensees' Environmental Report, as supplemented and amended.

B.

Subject to the conditions and requirements incorporated herein, the Commission-hereby licenses:

EA (1) Jy:t= 5:r;; t=r:n, :::. (!!") pursuant to Section 103 I

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of the 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; gg}

(2) System Energy Resources. Inc. and South Mississippi Electric Power Association to posses he facility at the designated location in Claiborne County, Mississippi, in accordance with the procedures and limitations set forth in this license; Amendment No. 27, l

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(3) A464t, pursuant to the Act and 10 CFR part 70, to receive, possess and use any any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts' required for j

reactor operation,:as. described in the Final Safety Analysis Report -

u as supplemented and amended; l

E4f (4) A6644, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive. l possess, and use at any time any byproduct, source and special i

nuclear material as. sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring-i equipment calibration, and as fission detectors in amounts as required; 40.2*

(5) A6546, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct.

l 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 EOZ (6) A6EM, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to l

possess, but not separata, such byproduct and special nuclear j

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materials as may be produced by the operation of the facility.

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(7) (a) SERI is authorized.to transfer up to 15 percent of its 90.0%

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• 1 ownership share in Grand Gulf Nuclear Station, Unit 1 (GGNS l

K Unit 1)..to certain equity investors identified in the submissions.of-October 31, 1988 and November 11, 1988, and at j

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 leaseback transactions are subject to the condition L

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 j

may be exercised only in compliance with and subject to the requirements and restrictions of this operating license, the j

Atomic Energy Act of 1954, as amended, and the Commission's.

regulations.

For purposes of this condition, the limitations of 10 CFR 50.81, as now in effect and as they may be subsequently 1

amended, are fully applicable to the lessors and any successors in interest to those lessors, as long as the license for GGNS Unit I remains in effect.

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SF-OL - 3 Amendment No. 54, l

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(b) SERI:is required to. notify the NRC.in writing prior to any change in (i) the tems or conditions of any new i

or existing sale or lease agreements-executed as part of the above authorized financial transactions,:(11) the

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GGNS Unit.1 operating agreement,-(iii) the existing property insurance coverage for GGNS Unit 1 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 addition, 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

-conditions'specified in the Consission's regulations set fcrth in 10 CFR Chapter.I.and is. subject to all applicable provisions of the Act and to the rules, regulations, and orders of:the Consission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level E0%.

AeERE is authorized to operate the facility at reactor core -

-f power levels not in excess of 3833 megcwatts thermal (100%

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. 64 are hereby incorporated into this license.

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N4as.shalloperatethefacilityinaccordancewiththe Technical Specifications and the Environmental Protection Plan.

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(3) Antitrust Conditions

@) MP&L and SERI shall comply with the antitrust conditions-1 delineated in Appendix C.

MP&L is authorized to transfer its rights to' possess, to.use'and to operate the facility to SERI, J

provided however :that until further authorization of the Com-mission, MP&L and SERI shall continue to be responsible for compliance with the obligations imposed on the licensees in these antitrust conditions,_and provided further that SERI accepts the right to possess use and operate the facility-sub.iect to the outcome of the Dunding separate antitrust review (b} of the antitrust consideration

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(4)

Independent Verification of Staff Performance and Other Plant Activities (Section 13.4, 5ER, 55ER #2) v Nt (a)W-66A4-shall establish a subcomittee of the Corporate Safety l-A Review Connittee to review and evaluate the:

l (i) Status and readiness of the plant and systems needed to support intended modes of operation and/or testing; i

.(ii) Readiness of personnel to conduct intended operation and testing;-

(iii) Morale and attitudes of. plant ' personnel that have a bearing on safe plant operation; h

(iv)Pastperformanceinplantoperationsand: adherence l

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 Conni ttee- (PSRC),

(vii)StatusofplantascomparedtootherBWRstartups based on the subcomittee's knowledge and experience.

Reviews shall be conducted prior to exceedino 50 percent of full power and within 30 days following completion of the o

The subconnittee shall be composed pKl L-100 hour warranty run.

y of a minimum of three professionals not employees of 3.4A+A with experience which will be responsive to the concerns presented above.

In conducting these evaluations, the Amendment No. 27 l

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.(b)f i MP&L and' SERI, are responsible ; and 'accotintable Jfor.l the" actions t ofl their

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1 subcommittee.shall conduct interviews of representatives of all; levels of plant staff management. The subcomittee shall report directly to the Chairman of the Corporate.

i Safety _ Review Comittee and, in_ turn,44EA+ shall-submit the'

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' report of these reviews to~NRC.

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'(b) _ The Plant Safety Review Comittee 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 per '

.formance of the portion of the Unit l'Startup_ Program being perfomed.. The review shall-address, as a minimum, a

system interaction, span of control, staffing, procedures -

security:and health physics.,with respect to performance of-the~

activities concurrent.with'the portion of-the Unit 1 Startup:

Program being performed.

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>(5) Deferred-Preooerational Deficiencies c J g + sh'all satisfactorily resolve those deficiencies which were A4EA deferred from the-preoperational testing' program on a schedule L

that shall: assure that the capability of a ' system required to i_ ;ir be operable by Technical Specification is not degraded.

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[(6)" Soil Structure Interaction (Section 3.7.1, SER, $$ER #2 Priortostartupfollowingthefirstrefuelingoutage,)$EAtshall l

complete structural modifications,.if required, as a result of-the NRC staff's completion of its' review of MP&L* responses..

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(7)l Seismic Instrumentation (Section 3.7.4, SER, SSER #2)'

Prior to startup following'the first refueling outage, the installation of triaxial strong motion accelerometers on reactor supports shall be completed.

(8) Masonry-Walls (Section 3.8.3, SER, SSER #2)

Alb Prior to startup following the first refueling outage, shall complete structural modifications, if required, as a result of the NRC staff's completion of its review of the MP&L response to IE Bulletin 80-11.

(Aunsafme.& 27 Aw?Norhad SEKZ?8 DP*N*N*N

• The original license authorized Mississippi Power & Light Company (MP&L) lE to operate'the facil Consequently, there are certain historical references to MP in this license, ghd SERI,lM NMfaSY rNeS SS Of*Y b Y E b C S CNI g

Amendment No. 27) l

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(9) Dynamic Testino ($ection 3.9.2, $ER, $$[R #2, $$ER #4, $$ER #5)

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]' 46M shall conduct vibrational measurement and inspection pro-l erams during preoperational and initial startup testing in

.accordance with the guidelines of R.G. 1.20, " Comprehensive Yibration Assessment Progreca for Reactor Internals During Pre-t operational and Initial $tertup Testino," for prototype reactors.

An evaluation report demonstrating sat < sfactory results shall be previded to the NRC for review and approval no later than 6 months after completion of the startup test progree.

1 (10) Dynamic Ovalification (3.10 $ER, $$ER #1, $$ER #2, $$tR #4, 33tm f5)

(a) Prior to startup following the first refueling outage l

thall complete any modifications or rep 14coment of equ pment found necesser as a result of the fatigue evaluation.

In sne inter'e shall document the occurrence of every 1

Mb safety reli valve actuation into the suppression pool; the associated cumulative damage factors shall be calculated for typical representative equ' paent and kept up to-date anQ)GG shall report tc NRC any malfunction of equipment I

that occurs due to any safety relief valve discharge, p,F 1 (b)M shall perform an in situ test of the High Pressure l

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Core Spray (NPCS) service water pump and eva' vate the effects of flow induced vibration on the NPC$ service water pump. This evaluation shall be provided to the NRC for review and aanroval. Prior to startup followino the first L.

refueling outage.hMM-shall complete all modif' cations as I

a result of the NRC staff's review of the test results and evaluation.

(c) Prior to actual use in fuel handling operations,Ac H & shall l

qualify the fuel-handling and auxiliary platform, in-vessel rack, and storage container for defective fuel.

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(11)EnvironmentalOvalifiestin(Section3.11,$ER:$$ER#11 Appereta M, 33tn rz; h!.

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Prior te March 31,1986 sha 1 environmentally qualify all l

i electrical equipment as required by 10 CFR 50.49.

(12)SurveillanceofControl51ade($ection4.2.3.14,$ER)

Within 30 days after plant startup following the first refueling outage, SERI shall comply with items 1, 2 and 3 of Bulletin No.

l 79-26 and submit a written response to NRC on item 3.

Amendment No. 27; l

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(13) Core Stability Analysis and Prohibition of Natural Circulation (5ect'on 4.4.m. 5ER)

(a) Prior to startup following the first refueling outage.

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shall submit a new core stability analysis for operation beyond cycle 1.

(b) Natural circulation shall be prohibited as an operating mode.

(14) Loose Parts Monitorig(Section 4.4.1, $ER) g Prior to startup following the first refue. ling outage.

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shall submit an evaluation of the Loose Parts Monitori

$ystem i

to address conforinance to R.G.1.133. Rev.1, dated May 1981.

(15)$cramDischeroeVolume ($ections 4.6, $ER) l Prior to startup followinq the first refueling outage, I.

shall incorporate the fol'owing additional modifications into the scram discharge volume system:

(1) Redundant vent and drain valves, and l

(ii) Diverse and redundant scram instrumentation for each instrumented volume, including both delta pressure sensors j

and float sensors.

(16)ContainmentPurce(Section6.2.4,$$ER#5) gp Prior to startup following the first refueling outage, shall I

provide for NRC review a reevaluation of the need to use the con-l tainment 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 airborne activity 'evel (ALARA).

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g overall containment air cua'ity and norsonnel access to contain-g ment. Based on the above c ted study,A46M shall propose the c

purge criteria to be used for the remainder of the plant life.

(17)ContainmentPressureBoundary($ection6.2.8,$ER)

Prior to startup fc110 wing the_ first rwfueling outage,AGEM shall I

replace the feedwater check valve disc with a disc made from a suitable material.

(18) Pressure Interlocks on Yalves Interfacino at low and High Pressure (5ection 6.3.4. 55ER #2)

Prior to startup following the first refueling outage, the licensee shall implement isolation protection against overpressurization of the low pressure emergency core coo ing systems (RHR/LPCI and LPCS) at the high snd low pressure interface containing a check valve and a closed motor operated valve.

Amendment No. 27,_

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(19) 1E Inforntion Notice 79 22, Qualification ef Control Syrte.

(Section 7.6.0, bER, 55ER 82)

Prior to startup following the first refueling outage.A66M-shall ll complete any design changes found necessary as a result of this review.

(20) Standby Service Water System (Section 9.2.1 SER. SSER 82)

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(21) Spent Fuel Pool Ventilation Systen (Section 9.4.2, SER, $$ER d2)

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!I 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 shutdown with the RHR system t

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dedicated to the fuel pool cooling mode.

l (22) Remote Shutdown Panel (Section 9.5.4.1, SER, $$ER e2)

Prior to startur following tne first refueling outage.446H-shall install. electrical isolation switches between the control room and the Divisicn 1 remote shutdown panel.

(23) Fire Protection procram (Section 9.5.9, SER) i 2 01 A46M shall maintain in effect and fully implerrer.t all g revisions of the approved Fire Protection Plan.

In addition, p

A MN4 shall maintain the fire protection prograrr to meet the l,'

intent of Appendix R to 10 CFR Part 50, except that an oil collection system for the reactor coolant pump is not required.

i SF-OL - 2 Amendment No. 34,_

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9-(24)

'nterolent Comunication Systems (Section 9.6.1.2, $ER, $$ER #2, H3tR 94, 55ER F5)

Tests of the comunication systems used to mitigate the con-sequences 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.

j (25)ReliabilityofDiesel-Generators ($ections 8.3.1,9.6.3 through 9.5.7, 5tR, 55[R FZ, satn #4, 33ER #6)

Jutage, a

.l (a) Priortostartupfollowingthefirstrefuelinkallbe heavy duty turbocharger gear drive assembly s installed on all EMD diesel-generators.

E0Z (b) A4EM-shall comply with TDI emergency diesel generator require-l{:

ments specified in Attachment 2 to this license.

(26)TurbineDiscintecrity(Section10.2.1,$ER,$$ER#1) 595 A4EM shall ultrasonically inspect the bores and keyways of the low l l pressure turbine discs for indications of cracking prior to exceeding l

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$0.000 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

4 operation. These inspections shall continue on a 50,000 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> interval until the potential for turbine disc cracking has been assessed and an acceptable alternate inspection schedule has been established.

(27)CirculatinoWaterSystem(Section10.4.5,SER)

I b shall not fill the Unit 2 circulating water system (including I

the natural draft cooling tower basin) until Unit 1 flooding concerns related to this system are resolved to the satisfaction of the NRC t

staff.

(28)AdvisortotheVicePresident NSEM shall have on its nuclear operations staff, one or more corporate l

management officials or advisors (who may be either permanent employees or contracted consultants) who have substantial comercial 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 905 of full power.

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Amendment No. 27) l

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(29)OperatinoShiftAdvisor(Section13.1.2,SER) f At least one individual on each operatino shift shall have substantive previous 8WR operating experience, including startup and shutdown of a BWR and under conditions that one might expect to'

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encounter during the initial startup and power escalation at the Grand Gulf plant..This individual is not reautred to be licensed on t

Grand Gulf Unit 1 and need not be a $6A4Aemployee, but as a minimum l!

shall be retained on a contract basis to act as a consultant or advisor to the GGNS shift crew.

Such sn experienced person shall be assigned to each operating shift until the plant achieves and demonstrates full power operation.

t (30)TraininoInstructors(Section13.2,SER) i

[ DELETED) f (31) Initial Test Procram (Section 14, SER)

/MN 4644 shall conduct the post-fuel-loading initial test program (set r

forth in Section 14 of/?!!!'; 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 modifications are defined as:

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(a) Elimination of any test identified in Section 14 of,J:0:';

l Final Safety Analysis Report, as amended, as essential; Ms.

(b) Modification of test objectives, methods r Teceptance criteria for any test identified in Section 14 of)mat % rinal Safety li Analysis Report, as amended, as being essential; (c) Performance of any test at a power level different from that described in the program; and (d) Failure to complete any tests included in the described program (planned or scheduled for power levels up to the authorized i

powerlevel).

I SF-OL - 10 Amendment No. 51, l

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11 (32) Partial Feedwater Heatino (Section 15.1, 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.

I (33) NUREG-0737 Conditions (Section 22.2) g

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C l ;h11 ;e.,ht: Ihefollowingconitiondtethesatisfaction of the NRC. These conditions reference the appropriate items in Section 22.2, *TMI Action Plan Requirements for Applicants for l

Operating Licenses", in the Safety Evaluation Report and Supple-ments 1, 2, 3, 4, and 5 NUREG-0831.

j (a) Control Room Desion Review (l.D.1, SER; Appendix E, SSER #2, 55ER f4, 55ER 95)

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 shut-i down 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 i

outdoor temperature of at least 95'F.

(b)' Train 1ncDurinolowPowerTestino(I.G.I.SER)

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Prior to restart following the first refueling outage, 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.

j (c) Post Accident Samplino(!!.B.3 SER, SSER fl. SSER #4,

iSER 75) _

Prior to startup following the first refueling outage, shall incorporate the additional requirements into the procedure for relating radionuclide Caseous and ionic species to estimate core damage as d'scussed in Section II.B.3.1 of SSER #4 j

(d) Hydrocen Control (Section !!.B.7,.SER, $5ER #2, SSER #3, 55ER f4, 55ER f5)

]

(1) During the first cycle of operation, shall 01 maintain a suitable program of analysis and testing of the installed hydrogen ignition system. SE4&

shall submit to the NRC quarterly reports on the status of their research programs.

Amendment No. 27 l

7

~.

g E0Z (a)/l6EM shall amend its research program on hydregen l

control measures to include, but not be limited to, the following items:

1)

Perfom containment sensitivity analysis to l

detemine the adequacy of the hydrogen control j

system for a spectrum of degraded core accidents including the determination of accident sequences for which equipment survivability is assured; s

2)

Research to investigate the conditions leading to and consequences resulting from hydrogen combus-tion in the wetwell and containment. Testing shall be perfomed in a larqer scale facility such as the one-quarter sco' e test facility proposed by MP&L; 3)

Research to investigate the conditions leading to and consequences resulting from hydrogen combustion in the drywell; 4)

Confimatory tests on thermal response of sel'ected equipment exposed to hydrogen burns, j

(b) ASEM-shell perform feasibility studies to examine the I

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 themal shielding, I

additional cooling, and relocation of essential equipment.

EQI I

l (2)

(a)AGEM shall complete its research program on hydrogen control to show that the hydrogen control system will perfom its intended function in a manner that provides adequate safety margins. This research program shall be completed on a schedule which reflects the require-ments of 10 CFR 50.44.

(b)

If it is determined that plant modifications are required to obtain NRC approval that an adequate f

hydrogen control system for Grand Gulf is installed.

then these modifications shall be completed on a l

schedule which is approved by the NRC.

(e)

Instrumentation for Detection of inadeounte Core Cooling II.F.Z, 5ER, 55ER F2) shall submit a report addressing the analysis performed I

by the BWR Owners' Group regarding additional instrumentation relative to inadequate core cooling and shall implement the Amendment No. 27,

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1 i 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.

(f) Modification of Automatic Depressurization System Loaic -

i Fossibility for Increased Diversity for Some Event Seouences (LI.K.3.18, SER, 55ER, #2, SSER #4)

Prior to startup following the first refueling outage, shall provide, for NRC review, justification for the timer delay setting's, revisions to the emergency procedures covering the use of the manual inhibit switch, proposed Technical Specification surveillance procedures for the timer and switen, and shall implement alternative logic modification (Option 4) of the automatic depressurization system.

(g) Qualification of ADS Accumulators (II.K.3.28, SSER #5) h Prior to startup following the first refueling outage, shall perform an integrated leak test on the ADS air system, perform sampling to establish instrument air quality, provide instrumentation to monitor ADS air receiver pressure, establish i

suitable surveillance procedures for the ADS air system and

(

provide proposed changes to the Technical Specifications associated with the surveillance procedures.

l (34) SRV Test Program (Section A-39, Appendix C, SER, SSER #1, SSER #2) i 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.

(35) Post-LOCA Vacuum Breaker Position _ Indicators 1

Prior to startup following the first refueling outage, shall j

install position indicators with redundant indication nd alarm in the control room for the check valves associated with the drywell 1

post-LOCA vacuum breakers.

(36) Emergency Response Facilities (Generic Letter 82-33, NUREG-0737 Supplement 1, SSER #5)

E0I dMA+shallcompletetheemergencyresponsecapabilities,asrequired by Attachment 17 = r:d:d thr::;5 5:nd::nt %. 53 t; t2 'i::n;c.

(37) Evaluation of Licensee's Technical Specification Problem Sheets (Section 16.3, SSER #6)

Prior to startup following the first refueling outa shall l

implement the following modifications:

SF-OL - 13 Amendment No. 53, l

1 14 l

(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 diesel

. generator to the emergency standby mode.

(!temNo.333, T.S. 4.8.1.1.F.d.12.b) i (b) Provide the second level undervoltage protection for Division 3 power supply (! tem No. 373. T.S. Table 3.3.3-2).

(c)

Incorporate a bypass or coincident logic in all Division 1 and 2 diesel generator protective trips, except for trips i

on diesel engine overspeed and generator differential current (! tem No. 408. T.S. 4.8.1.1.2.d.16.d).

(38) Control Room Leak Rate (Section 6.2.6. SSER #6)

StZ A4EA& shall operate Grand Gulf Unit I with an allowable control t ;.

room leak rate not to exceed 590 cfm. Upon restart of construc-tion of Unit 2 control ro will be pemitted to operate at l

a leak rate of 760 cfm as ted in $5ER No. 6.

a (39) Temporary Secondary Containment Boundary Chance For a period of time not to exceed 144 cumulative hours, the l

provisions of Specification 3/4.6.6.1 may be applied to the rail-i road bay area including the exterior railroad bay door on the auxiliary building in ' teu of the present secondary containment boundaries that isolate the railroad bay area. While the rail-road bay area is being used as a secondary containment boundary, the railroad bay door may be opened for 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 Chance i

With the plant in OPERATIONAL condition 4. $$W cooling tower basin A may be considered 0PERABLE in accordance with Technical Specification 3.7.1.3 with less than a 30 day supply of water l

(without makeup) during the time that $$W basin 8 is drained to j

j.

replace its associated service water pump provided:

(a) $$W basin A water level is maintained greater than or equal to 87".

L (b) At least two sources of water (other than normal makeup l

with one source not dependent on offsite power) are L

available for makeup to $$W basin A.

l l

This license condition may remain in effect until plant startup l~

following the outage scheduled for fall 1985.

Amendment No. 27, l

I o 0; l

6. D.

The facility required exen tions 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 1

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 !!!.D.2(b)(ii) of Appendix J for the containment airlock i

testing following nonnal door opening when containment integrity is not i

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 Comission exempted licensees 1

from 10 CFR 100,11(a)(1), insofar as it incorporates the definition of l

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 l

with the common defense and security.

In addition, special 1

circumstances have been found justifying the exemption. Therefore, 1

these exemptions are hereby granted pursuant to 10 CFR 50.12. With the j

granting of these exemptions, the facility will operate, to the extent with the application, as amended, the authorizedherein,inconformit{esandregulationsoftheCommission.

provision of the Act and the rus l

E.

The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments L

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).

l Theplans,whichcontainSafeguardsInformationprotectedunder 10 CFR 73.21, are entitled:

Grand Gulf Nuclear Station Physical

.i Security Plan " with revisions submitted through September 1, 1987; j.

" Grand Gulf Nuclear Station Guard Training and Qualification Plan,"

l L

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 accordance with the schedule set forth therein.

S0.5 l

F. QEni shall report any) violations of the requirements contained inSec 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).

i and(e),

l L

Amendment No. 44 7,_ :

SF-OL - 15

$v $ttkr or) 0Mh A

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16 G.

The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shell require in accordance with Section 170 of the Atomic Energy Act of 1954 as amended, to cover pubite liability claims.

4 H.

-This license is effective as of the date of issuance and shall expire at midnight on June 16, 2022.

FOR THE EAR REGULATORY C0m!5$10N.

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)

/

arold R. Denton. Director i

Office of Nuclear Reactor Re9ulation Attachments:

1.

2.

Appendix A - Technical

$pecifications(NUREG-0934) i 3.

Appendix B - Environmental Protection Plan 4.

Appendix C - Antitrust Conditions i

Date of !ssuance: November 1, 1984 l

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i NOVEMBER 1, 1984 i

i 4EM shall complete the following requirements on the schedule noted below:

Eneroency ResDonse Facilities (Generic Letter 82-33. NUREG-0737 luDDlement 1. 55tR F5)

(

4644 shall implement the specific items below, in the manner described in l!

MP&L letter (AECM-83/0232) dat'd April 15, 1983, as modified in NP&L e

lett.or(AECM-43/0486) dated August 22, 1983, no later than the following specified dates:

l (a) Safety Parameter Otsplay System (SPOS)-

p (1) Submit a safety analysis and implementation July 1985 plan to the NRC (2) SPOS fully operational and operator tra'ned Prior to startup following first refueling outage.

(b) Detailed 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 requirements of Supplement 1 to NUREG-0737 have been or will be met, i

(2) Implement (installationorupgrade)

Prior to startup requirements of R.G. 1.97 with exception following first of flux monitoring and coolant level monitoring, refueling outage.

(3) Implement (installation or upgrade)

Prior to startup requirements of R.G.1.97 for coolant level following second monitoring, refueling outage.

(4) Implement (installation or upgrade)

Prior to startup requirements of R.G.1.97 for flux monitoring.

following fourth refueling outage (d) Upgrade Energency operating Procedures (E0P's)

(1) Submit a Procedures Generation Package to the April 1985 NRC.

Amendment No. 53,-

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(2) ~!aplement the upgraded 10p's Prior to startup 3

following the h

first refueling outage (e) Emergency Response Facilities (1)'

Technical Support Center fully functional Prior to startup with exception of Regulatory Suide 1.97 following the implementation first refueling i

outage (2)

Operational Support Center fully functional prior to startup 6

with exception of Regulatory Guide 1.97 following the implementation first refueling outage (3)

Emergency Operations Facility fully Prior to startup functional with exception of Regulatory following the Guide 1.97 implementation first refuelirg muy

(

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j

,?

Transamerica Delaval Inc. (TDI) Diesel Generator Maintenance and Surveillance Recuirements (NUREG-1216. Auoust 1986) l I

1.

Maintenance and Surveillance Proeram i

EoK 49Ett shall implement and maintain in effect the provisions of the main-l>t tenance and surveillance program for the TDI emergency diesel generators i

at GGNS Unit 1 as identified in the MP&L letter dated July 18, 1986 i

(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.

Chances 4%

/]4EM-may make chan0es to the approved maintenance and surveillance lI program without pr'or approval of the Commission provided the changes do not adversely affect the operability or reliability of the diesel generators or involve changes in the Phase ! Surveillance requirements of I

paragraph 3 below or otherwise change license conditions or Technical Spec < fications or result in an unreviewed safety question as defined in E

10 CFR 50.59.A4EE shall maintain in auditable fom, a current record of I;

all such changes, including an analysis of the effects of the change on l

diesel generator operability and reliability, and shall make such records availab' e to NRC inspectors upon request.. All changes to the program shall l

be reported annually to the Director of the Office of Nuclear Reactor i

Regulation, along with the FSAR revisions required by 10 CFR 50.71(e).

i 3.

Phase 1 Component Surveillance Recuirements

$ b shall comply with the following requirements:

I*

3.1 Connectine Rods Connecting rod assemblies shall be subjected to the following inspections at each major engine overhau1*:

l a.

The surfaces of the rack teeth shall be inspected for signs of fretting.

If fretting has occurred, it shall be subject to an L

engineering evaluation for appropriate corrective action.

I i

The frequency of the major engine overhauls referred to in these requirements i

shall be consistent with Section IV.1.

" Overhaul Frequency" in Revision 2 of Appendix !! of the Design Review /Ouality Revalidation report which was transmitted by MP&L letter dated July 18, 1986.

L Amendment fio. 27,-

9

y-[h 5f? A O

-z-i b.

All connecting rod bolts shall be' lubricated in accordance with i

the engine manufacturer's instructions and torqued to the spect.

j fications of the manufacturer. The lengths of the two pairs of i

bolts above the crankpin shall be measured ultrasonically pre and post-tensioning.

c.

The lengths of the two pair of bolts above the crankpin shall

.i:

be measured ultrasonically prior to detensioning and disassembly

)

-of the bolts. If bolt tension is less than an equivalent of 2400 ft-Ibs, the cause shall be detemined, appropriate 1

corrective action shall be taken, and the interval between l

checks of bolt tension shall be re evaluated.

d.

All connecting rod bolts shall be visually inspected for thread-damage (e.g., galling), and the two pairs of connecting rod l

bolts abcVe the crankpin shall be inspected by magnetic particle

{

testing (MT)toverifythecontinuedabsenceofcracking. All washers used with the bolts shall be examined visually for signs of galling or cracking, and replaced if damaged, e.

A visual inspection shall be performed of accessible external surfaces of the link rod box to verify the absence of any signs

(

of service induced distress.

('

f.

A11'of the bolt holes in the link rod box shall be inspected 4

forthreaddamage(e.g., galling)orothersignsofabnormalities, t i In addition, the bolt holes subject to the highest stresses (i.e..

I the pair immediately above the crankpin) shal' be examined with

)

an appropriate nondestructive method to verify the continued I

absence of cracking. Any indications shall be recorded for T'

enoineering evaluation and appropriate corrective action, g.

If the diesel generators are operated in excess of 5740 W steady state, all connecting rods shall be disassembled and inspected l

at an interval of approximately 5 years coincident with the end of a fuel cycle, except that connecting rod disassembly and inspection is not required for limited post maintenance testing over 5740 W for the purpose of seating new piston rings as described in the MP&L letter dated December 6, 1985 (AECM-85/0395).

3.2 Cylinder Blocks a.

Cylinder blocks shall be inspected for " ligament" cracks,

" stud-to-stud" cracks and " stud-to-end" cracks as defined in a l

L report by Failure Analysis Associates, Inc. (FaAA) entitled,

)

" Design Review of TDI R-4 and RV-4 Series Emergency Diesel Generator Cylinder 81ocks" (FaAA report no. FaAA-84-9-11.1) dated December 1984.**

(Note that the FaAA report specifies Transmitted to H. R. Denton, NRC from C. L. Ray, Jr., TDI Owners Group, by letter dated December 11, 1984 l

, qp y-k h o s 'b i ry i

s:

-3 additional inspections to be performed for blocks with "known" or" assumed"ligamentcracks). Theinspectionintervals(i.e.,

frequency) shall not exceed the intervals calculated using the cumulative damage index model in the subject FaAA report.

In addition, inspection method shall be consistent with or equivalent to those identified in the subject FaAA report.

b.

In addition to inspections specified in the aforementioned FaAA report, blocks with "known" or " assumed" ligament cracks (as defined in the FaAA report) shall be inspected at each refueling outage to determine whether or not cracks have initiated on the top surface exposed by the removal of two or.more cylinder heads. This process shall be repeated over several refuelino outages until the entire block top has been inspected. Liquid-t penetrant testing or a similarly sensitive nondestructive testing technique shall be used to detect cracking, and eddy current shall be'used as appropriate to detemine the depth of any cracks discovered.

c.

If inspection reveals cracks in the cylinder blocks between stud holes of adjacent cylinders (" stud-to-stud" cracks) or

" stud to-end" cracks, this condition shall be reported promptly to the NRC staff and the affected engine shall be considered inoperable.

The engine shall not be restored to " operable"

(

L status until the proposed disposition and/or corrective actions l

have been approved by the NRC staff.

}

3.3 Cylinder Heads 4

l ~

l The following air roll test shall be perfomed as specified below, except when the plant is already in an Action Statement of Technical Specification 3/4.8.1, " Electric Power Systems A.C. Sources":

(-

The ancines shall be rolled over with the airstart system and with the cy'inder stopcocks open prior to each planned start, unless that start occurs within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of a shutdown. The engines shall also be rolled over with the airstart system and with the cylinder stopcocks open after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, but no more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after engine shutdown and then rolled over once again approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after each shutdown.

(!n the event an eng'ne is removed from service for any reason other than the rolling over procedure prior to expiration of the 8-hour or 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> periods noted above. that engine need not be rolled over while it is out oc service. The licensee shall air roll the engine over with the stopcocks open at the time it is returned to service.) The origin of any water detected in the cylinder must be detemined and any cylinder head which leaks due to a crack shall be replaced. The above air roll test may be discon-l tinued following the first refueling outage subject to the following conditions:

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-4 e.

All cylinder heads are Group !!! heads (i.e. cast after September 1980.)

b.

Quality reve11dation inspections, as identified in the GGNS Design Review / Quality Revalidation Report, Revision 2. have l

been completed for all cylinder heads, c.

Group !!! heads continue to demonstrate favorable leakage performance. This should be confirmed with TDI prior to deleting air roll tests.

7 3.4 Turbochargers Periodic inspections of the turbochargers shall include the following:

a.

The turbocharger thrust bearings shall be visually inspected for "r

excessive wear after 40 non prelubed starts since the previous j

visual inspection.

3 b.

Turbocharger rotor axial clearance shall be measured at each I

refueling outage to verify compliance with TD!/Elliott specifications.

In addition, thrust bearing measurements shall l

be compared with measurements taken previously to detemine a need for further inspection or corrective action.

l c.

~ Spectrographic and ferrographic engine oil analysis shall be l

performed quarterly to provide ear'y evidence cf bearing degradation. Particular attention shall be paid-to copper level and particulate size which could signify thrust bearing t

degradation.

d.

The nozzle ring components and inlet guide vanes shall be l

visually inspected at each rti'veling outage for missing parts or parts showing distress.

If such are noted, the entire ring i

assembly shall be replaced.

I s

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Novenbar 1. 19a4 j

l APPEN0!! C f

ANTITRUST CONDLTIONS Opth. Tins _ Lictnat in, wr.29 i

MP&L and SERI shall comply with the following antitrust conditions:

i 1

1 J.

CEFIN!T{g),

(a) ' Western Mississippi Aree' means the counties of: Walthall.

Lawrence. Jefferson Davis, Covington Simpson Smith. Scott.

l Leake. Attals. Choctaw. Montdomery, drenada Yalebusha. Panola, i

Tate. DeSoto, pike. Amite. Wilkinson.- Adams. Franklin Lincoln, i

Copiah, Jefferson Claiborne. Minds. Rankin. Madison. Yazoo.

l Warren. Issaquena. Sharkey. Humphreys. Nelmes. Carroll. Lefiere.

Sunflower. Washington. Bolivar. Tallahatchie. Quitman. Coahome.

and Tunica. An entity shall be deemed to be in the ' Western E

Mississippi Area" if it has electric power generation, transmis-sion, or distribution facilities located in whole er in part in i

the above described area.

l (b)

• Selk power' means the electric power, and any attendant energy.

supplied e/ made available at transmission er subtransmission weltage by one entity to another.

(c)

• Entity

• means a person, a private or public corporation, a i

municipality, a cooperative, an association, a joint stock i

l-association er business trust owning operating or proposing to own er operate equipment er facilitie,s for the generation, trans.

l mission er distribution of electricity, provided that escept for municipalities or rural electric cooperatives.

• entity

• is restricted to those which are or will be public att11 ties 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 er rate schedule en file with and subject to the regulation of a state regulatory commission er the Federal power Commission.

(d)

'Cest' means any operating and maintenance expenses involved together with any ownersh' p costs which are reasonably allocable to the transaction consistent with power pooling practices (whereapplicable).

No value shall be included for less of revenues from sale of power at wholesale or retail by one party to e customer which another party might otherwise serve. Cost shail include a reasonable return on Licensees' investment. The sale of a portion of the capacity of a generating unit shall be t

upon the basis of a rate that will recover to the seller the pro rata part of the fixed costs and operating and maintenance Amendment No. 27 l

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.L expenses of the unit, provided that, in circumstances in which licensees and one or more entities in the Western Mississippi Area take an undivided interest in a unit in fee, construction i

costs and operation and maintenance expenses shall be paid pro-i rata.

l l

INTERCONNECTION $

(a) Licensees shall interconnect with and coordinate reserves by means of the sale and purchase of emergency and/or scheduled maintenance bulk power with any entity (ies) in the Western Mississippi Area engaging in or proposing to engage in electric bulk power supply on terms that will prqvide for Licensees' costs in connection therewith and allow the other party (ies) full access to the benefits of reserve coordination.

1.

(b) Emergency service and/or. scheduled maintenance service to be provided by each party shall be furnished to the fullest extent i

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 generhtion an( from generation of others to the extent it can do to without impairing service to r

its customers including other electric systems to whom it has firm cosnitments.

Licensees and the other party ies) to a reserve sharin arrange-l (c) ment shall from time to time ointly establish the einfaum reserves to be installed and/or provided under contractual t

arrangements as necessary to maintain in total a reserve margin sufficient to provide adequate reliability of power supply to the interconnected systems of the parties.

If Licensees plan ggt Q Mo '

their reserve margin on a pooled basis with other M4dd+e-Goet*-

l O

A b 64em companies, the reserves jointly established hereunder stall 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 arrangement shall be required to maintain greater reserves than the per-contage of its estimated peak load responsibility which results from the aforesaid calculation, provided that, if the reserve j

requirements of Licensees are increased over the amount Licensees would be required to maintain without such interconnection, then the other party (fes) shall be required to carry or provide for as its (their) reserves the full amount in kilowatts or such J

increase.

(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 Ainend mc k Wo -

or Zkovaboh Or

,

• demands on the other in meeting the nomal contingencies of

- operating its system. However, in no circumstances shall the ready reserve requirement exceed the installed reserve require-t ment.

1 L

(e)

Interconnections will not be limited to low voltages when higher voltages are available from licensees' installed facilities < n '

the area where interconnection is desired, when the proposed arrangement is found to be technically _and economically feasib10.

i Control and telemstering facilities shall be provided as required l

for safety and prudent operation of the interconnected systems.

l l

(f)

Interconnection and coordination agreements shall not-embody any l

restrictive provisions pertaining to intersystem coordination.

f Good industry practice as developed in the area from time to time (if non-restrictive) will satisfy this provision.

i

!!!. p0WER TRANSACTION $

Licensees will sell bulk power at their costs to or purchase bulk power

]

from any other entity (tes) in the Western Mississippi Area engaging in or proposing to engage in generation of electric power when such l

t transactions would serve to reduce the overall costs of new bulk power 1

L supply for themselves or for the other party (ies) to the transaction.

J This refers specifically to the opportunity to coordinate in the This planning of new generation, transmission and related facilities.

Provision shall not be construed to require Licensees to purchase or 1

i sell bulu power if they find such purchase or sale infeasible or their costs in connection with such purchase or gale would exceed their i

benefit therefrom.

1 i

4 IV.

PARTICIPATION IN OWNER $ Hip Licensees and any successor in title shall offer an opportunity (a) to participate in the Grand Gulf Nuclear Units and any other nuclear generating unit (s) which they or either of them, may construct. own and operate in the $ tate of Mississippi, severally 1

or jointly, during the term of the instant license, or any extension or renewal thereof, to any entity (ies) in the Western Mississippi Area by either a reasonable ownership interest in such unit (s), or by a contractual right to purchase a reasonable portion of the output of such unit (sJ at the cost thereof if the entity (ies)soelects.

In connection with such access, licensees will also offer transmission service as ma'y be required for delivery of such power to such entity (ies) on a basis that will fully compensate licensees for their cost.

t 4

e 1

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,(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 l

more nuclear generating units constructed, owned and operated by)-

any affiliate or subsidiary of M" u 2= Mut; ",;Q other than licensees, or by any successor in title to the Grand Gulf Nuclear Units, licensees shall esert their best efforts to obtain participation in such nuclear unit (s). by any entity (ies) i in the Western Mississippi Area requesting such participation on j

terms no less favorable than the terms of licensees' participa-i' tion theretn.

V.

TRANSMIS$!0N $[RVICl3 (a). Licensees shall facilitate the exchange of bulk power by trans-i mission over its transmissicn facilit'es between or among two or more entities in the Western Mississippi Area with which it is i

interconnected; and between any such entity (ies) and any such edity(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 electricalpath,providedthat(1)permissiontoutilizesuch other transmission lines has been obtained, and (t) the arrange-meats reasonably can be accommodated from a functional and tech-nical standpoint.

Such transmission shall be on terms that

• fully compensate Licensees for their cost. Anyentity(ies) j regoesting such transmission arrangements shall give reasonable advance notice of its (their) schedule and requirements.

(The l

foregoing applies to any entity (ies) to which Licensees may be interconnected in the future as well as those to which they are nowinterconnected.)

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(b) Licensees shall include in their planning and construction pro-gram sufficient transmission capacity (a)s required for the trans-a actions referred to in subparagraph of this parafiraph.

providedthatanyentity(ies)intheWesternMississ'ppiArea i

give Licensees sufficient advance notice as may be r.ecessary to accomodate 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 benefit to Licensees.

g VI. POWER FOR RESALE Licensees will sell power for resale to any entity (its) in the Western Mississippi Area now engaging in or proposing to engage in retail distribution of electric power.

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l V!!. REG lLATORY PROV!510NS The foregoing conditions thall be implemented in a manner consistent with the provisions of the Federal Powr Act and the Mississippi Public Utilities Act of 1956 and all rates, charges or practices in connection therewith are to be subject to the approval of regulatory agencies having jurisdiction over them.

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l APPENDIX B TO FACILITY LICENSE N0. NPF-29 GRAND GULF NUCLEAR $TATION l

UNIT 1

[41999L%l*IMM!i $*

I DOCKET NO. 50-416 ENVIRONMEtlTAL PROTECTION PLAN t

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OCTOBER 1984

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' I Amendment No. 21 -

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ADMINISTRATIVE CONTROLS 6.5.2 SAFETY REVIEW Com ITTEE (SRC)

FUNCTION l

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 I

b.

nuclear engineering

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c.

chemistry and radiochemistry i

d.

metallurgy e.

instrumentation and control i

f.

radiological safety g.

mechanical and electrical engineering

[d usy r d s u, M c.

h.

quality assurance practices E

o COMPOSITION 6.5.2.2 The SRC shall be composed of a Chairman and nine voting members.

Two l

or more additional voting members shall be consultants tog-M Sn "n:rn;, l Int. consistent with the recommendations of the Advisory Coin;nittee onleactor j

Safeguards letter, Hark 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 i

to call consultants and contractors for dealing with complex problems beyond the scope of System Energy Resources, Inc expertise.

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 l

shall participate as voting members in 3RC activities at any one time.

1 GRAND GULF-UNIT 1 6-9 Amendment No. 64,_

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by the aerial surveys, and walking patrols will be directed to the problem areas to evaluate the extent of the problem to be corrected.

The Erosion Control Inspection Program shall begin upon commencement of normal transmission line inspection procedures.

Semi-annual surveys shall continue I

unti1' 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 main-i tenance activities shall be reported in the Annual Environmental Operation Report in accordance with Subsection 5.4.1.

Field logs ' indicating locations of erosion damage and measures taken to re,ctify erosion problem areas and estimation of the time to achieve effective stabilization will be maintained and available for inspection for a period of five years.

Results reported shall contain information encompassing but not limited to inspection date, estimated size of erosion problem area, probable cause of erosion, type of

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stabilization program, and date of effective stabilization, as appropriate.

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l 4.2.2 Coolino Tower Drif t Program Seven sampling sites will be utilized to measure cooling tower drift-deposition.

At least two of the sampling sites will have duplicate saepling devices.

Six of i

the seven sampling sites will be located in areas where maximum salt deposition I

is predicted.

These areas were extrapolated from the Bechtel Salt Deposition 66NS t

l Model developed for the 4EMAFinal Environmental Report.

The seventh sampling site 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, 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 solids.

These parameters were selected because l

past analyses have shown them to be prevalent in the cooling water source water.

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The results of these analyses will be correlated with local rainfall data and 4-2 Amendment No. 42 l

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