AECM-88-0241, Application for Amend to License NPF-29,revising Tech Spec to Support Cycle 4 Reload for Facility.Fee Paid.Repts Re Reload forwarded.ANF-88-183(P) Withheld

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Application for Amend to License NPF-29,revising Tech Spec to Support Cycle 4 Reload for Facility.Fee Paid.Repts Re Reload forwarded.ANF-88-183(P) Withheld
ML20196E890
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 12/06/1988
From: Cottle W
SYSTEM ENERGY RESOURCES, INC.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML19295G794 List:
References
AECM-88-0241, AECM-88-241, NUDOCS 8812120127
Download: ML20196E890 (12)
v • d • e


Text

- _.

REEOtAWEE,IIW.

December 6, 1988 U. S. Nuclear Regulatory Cormiission Mail Station P1-137 Washingtor;, D. C. 20555 Attention: Document Control Desk Gentlemen:

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No 50-416 License No. NPF-29 Cycle 4 Reload Proposed Amendment to the Operating License (PCOL-88/21)

AECM-88/0241 Syster. Energy Resuurces, Inc. (SERI) is submitting by this letter a proposed amendn'ent to the Grand Gulf Nuclear Station (GGNS), Unit 1 Operating License. This amendment pertains to those technical specification changes required to support the Cycle 4 Reload for GGNS.

In accordance with the provisions of 10 CFR 50.4 and 50.30, the signed [

original of the requested amendment is enclosed and the appropriate copies will be distributed. The attachment provides the technical justification and discussion to support the requested amendment. This amendment has been reviewed and accepted by the Plant Safety Review Committee and the Safety Review Corrinittee.

The amendment package under cover of this letter (provided as Attachment

3) :onsists of the follo,.ing components:
1. Description of Technical Specification (TS) changes
2. Justification of requested TS changes
3. No Significant Hazard Consideration Determination

$9 4. Marked-up TS pages gm 5. Grand Gulf Nuclear Station Unit 1 Cycle 4 Reload Summary Report Proposed Startup Physics Tests 6.

cah '

& 7. Advanced Nuclear Fuels Corporation (ANF) Technical Reports:

Mo a. ANF-88-149, "Grand Gulf Unit 1 Cycle 4 Reload Analysis" av November 1988 08 b. ANF-88-150, "Grand Gulf Unit 1 Cycle 4 Plant Transient CA Analysis" November 1988 U" c. ANF-88-183(P), "Grand Gulf Unit 1 Reload XN-1.3, Cycle 4 Og Mechanical Design Report" November 1988 Mo 8. NES00-88-003, "Grand Gulf Nuclear Station Unit 1 Revised Flow

  • Dependent Thermal Limits" November 1988 g g o ,p;3- l.oav. , <v ls un  : t/k4 s A//

s y S p. .v ..m L e s,n f 8 Of J14AECM88120201 - 1 dit/sekl/SO.*C bcl, fnr 4 gg.gyg I j

i AECM-88/0241 Page 2 As discussed with the NRC Staff on July 28, 1988 the Technical Specification changes reflect insertion of a new ANF fuel batch; introduction of four 9x9-5 Lead Test Assemblies; and revision of thermal limits for a full ANF core, based on ANF methodology. ,

To facilitate reload related procedure development, training, and testing activities in support of plant startup for Cycle 4 SERI requests your approval t of this proposed license amendment by March 24, 1989. (

Based on the guidelines presented in 10 CFR 50.92, SERI has concluded l that this proposed amendment involves no significant hazards considerations.  ;

In accordance with the requirements of 10 CFR 170.21, an application fee of $150 is attached to this letter Yours truly,  ;

t AY - CL-_- - l

k. T. Cottle Vice President, Nuclear Operations l l i WTC:jjb Attachments: 1. Remittance of $150 Application Fee
2. Affirmation per 10 CFR 50.30
3. GGNS PCOL-88/21  ;

cc: Mr. T. H. Cloninger (w/a)

Mr. R. B. McGehee (w/a) i Mr. N. S. Reynolds (w/a)

) 3

!'r. H.

Mr. H.O.L.Christenson Thbmas (w/o)(w/a) t l Mr. Malcolm L. Ernst, Acting Regional Administrator (v/a)

. V. S. Nuclear Regulatory Commission

! Region II i 101 Marietta St., N. W., Suite 2900 i Atlanta, Georgia 30323 l Mr. L. L. Kintner, Project Manager (w/a) l Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Cormission Mail Stop 14820 l Washington, D.C. 20555 Dr. Alton B. Cobb (w/a) l State Health Officer l

State Board of Health l Box 1700 l Jackson, Mississippi 39205 l

J14AECM88120201 - 2

( =

BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE NO. NPF-29 f'

DOCKET N0. 50-416 IN THE MATTER OF MISSISSIPPI POWER & LIGHT COMPANY ar1d SYSTEM ENERGY RESOURCES, INC.

and SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION AFFIRMATION I I, W. T. Cottle, being duly sworn, state that I am Vice President, 3

' Nuclear Operations of System Energy Resources, Inc.; that on behalf of System Energy Resources, Inc., and South Mississippi Electric Power Association I am authorized by Syste'n Energy Resources, Inc. to sign and file with the Nuclear Regulatory Comission, this application for amendment of the Operating License of the Grard Gulf Nuclear Station; that I signed this application as Vice President, Nuclear Operations of System Energy Resources, Inc.; and that the str.tements made and the matters set forth therein are true and correct te the best of my knowledge, information and belief.

WVM _

l W. T. Cottle 1

S.' ATE OF MISSISSIPPI C0bl'T OF HINDS SUCSCRIBE0 AND SWORN T0 be re me, a Notary Publip, in and for the County and State above named, this day of /UfA%46 ) , 1988.

(SEAL)

/J u , t u] YW I My commission expires:

r, c ,t- . s t.:t ::st 4

J14AECM88120201 - 4

SUBJECT:

NL-88/16, Technical Specification changes to address reload Cycle 4.

Technical Specifications 3/4.2.1, 3/4.2.4 and 5.3.1.

Figures 3.2.1-1, 3.2.1-Id, 3.2.1-le, 3.2.1-2, 3.2.3-1, 3.2.3-2 and 3.2.4-1.

Bases 2.1.1, 2.1.2, 3/4.2.1 and 3/4.2.3.

Affected Pages: 82-la, B2-2, 3/4 2-1, 3/4 2-2, 3/4 2-2d, 3/4 2-2e, 3/4 2-3a, 3/4 2-5, 3/4 2-6, 3/4 2-7, 3/4 2-7a, 83/4 2-1, 83/4 2-4, 83/4 2-6 and 5-5.

DESCRIPTION OF CHANGES:

1. Bases 2.1.1: (Administrative) Change "Exxon Nuclear Company" to "Advanced Nuclear Fuels Corporation". Change "ENO" to "ANF" at two locations.
2. Bases 2.1.2: (Administrative) Change "Once" to "One" and "ENC" to "ANF".

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3. Specification 3/4.2.1: Revise text to delete reference to fuel type 8CR210, to reference MAPLHGR curves for one new 8x8 fuel type and new 9x9-5 Lead Test Assemblies (LTAs), and to defineSinn'eLoopOperation(SLO)limitforthe9x9-5 LTAs.

4 Figure 3.2.1-1: Revise the figure to provide a bounding MAPLHGR curve for Cycle 4 for all 8x8 fuel during single loop operation. Change title of figure.

5. Figure 3.2.1-1d: Add one MAPLHGR curve for new ANF 8x8 fuel type.

v or new 9x9-5 LTA.

6. Figure 3.2.1-le: Add one MAPLHGR curvs-
7. Figure 3.2.1-2: Add MAPFAC curves for Non loop Manual and loop f

Manual modes based on full ANF core. Delete the 102.5%

and 107% maximum core flow MAPFAC f curves for ANF fuel and the 102.5% maximum core flow curve for GE fuel.

Revise the 107% maximum core flow MAPFAC f for GE fuel to delete that portion of the curve with MAPFACf greater than 0.06 and change the curve description.

8. Figure 3.2.3-1: Add MCPR curves for Non Loop Manual and Loop Manual f

modes based on full ANF core. Delete the 102.5% and 107% maximum core flow MCPR f curves.

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9. Figure 3.2.3-2: Revise the figure to show MCPR p limit based on full ANF Core.
10. Specification 3/4.2.4: Delete references to GE fuel LHGR.

(Administrative) Delete references to ENC.

11. Figure 3.2.4-1: Revise the figure to add one LHGR curve for new 9x9-5 LTA. (Administrative) Change title of figure.

(Administrative) Correct plotting error in the LHGR curve for 8x8 fuel type.

12. Bases 3/4.2.1: Add references to MAPLHGR curves for new ANF fuel types. Revise text to discuss revised MAPLHGR curve for single loop operation. Revise text to discuss ,

MAPF'C curves based on Loop Manual and Non loop Manual f

medes of operation. Delete description of flow runout to 102.5% and 107% of rated flow. Revise text describing the MAPFAC p curves.

13. Bases 3/4.2.3: Delete description of evaluation of transients for GE core. Revise text to discuss MCpR curves based on f

Loop Manual and Non Loop Manual modes of operation.

f I

I Delete description of flow runout to 102.5% and 107% of

! rated flow. Delete cycle-specific discussion for MCPRg .

)

(Administrative) Add reference for Figure B3/4 2.3 1 l

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'14 Specification 5.3.1: Rcvise text to generalize description for all Cycle 4 fuel types.

DISCUSSION:

Reasons for Changes The proposed Technical Specification changes reflect:

o Insertion of new ANF reload fuel batch loaded for operation during Cycle 4.

o introduction of four ANF 9x9-5 Lead Test Assemblies to deronstrate operational performance prior to full 9x9-5 reload in Cycle 5.

o Revision of thermal limits for full ANF core based on ANF calculational methodology.

Discussion of Changes Specification 3/4.2.1 is revised to add one MAPLHGR curve each for the new ANF 8x8 fuel type and 9x9-5 LTAs to be loaded in Cycle 4 The SLO MAPLHGR l

limit for the 8x8 ANF fuel is defined as the 8x8 SLO MAPLHGR value (Figure i

3.2.1-1) multiplied by the minimum of the SLO MAPFACf, MAPFAC p or 0.86.

The SLO MAPLHGR limit for the 9x9-5 LTA is defined as the 9x9-5 MAPLHGR multiplied by the minimum of the corresponding MAPFAC f, MAPFAC p or 0.86.

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Figure 3.2.1-1 is revised to pro, de a bounding MAPLHGR curve for Cycle 4 for all 8x8 fuel types durina single loop operation.

Figures 3.2.1 2 and 3.2.3-1 are revised to define flow dependent thermal limits, MAPFAC and MCPR , respectively, based on a conservative bound of 7 f the maximum credible recirculation flow. An increase to the maximum core flow is assumed to occur by the slow opening to the maximum open position of one or both of the recirculation flow control valves. Separate consideration is given to the "Locp Manual" and "Non Loop Manual" modes of For the Non Loop Manual modes, both valves are assumed to open 4 operation.

simultaneously since a single centroller determines the position of both i 1

recirculation flow control vr.lves. For the Loop Manual mode, the valve positions are controlled irdependently and only one valve can credibly be assumed to open. The MAPFAC f ard MCPR f curves for 10?.5% flow and 107%

flow are deleted and replaced by curves for the Non Loop Manual and Loop Manual operational modes. The 107% flow MAPFAC f curve for GE fuel is retained for use in determining the off-rated MAPLHGR during single loop operation. The p3rtion of this curve for MAPFAC f values above 0.86 is l

deleted.

I Figure 3.2.3-2 is revised to define MCPR p limits for Cycle 4 as a function j of power level. The limit is based on ANF methodology applied to a full ANF core.

Specification 3/4.2.4 is revised to delete referent.es to the LHGR for GE fuel.

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Figure 3.2.4-1 is revised to add one LilGR curve for the new ANF 9x9-5 LTA to be loaded in Cycle 4 The LHGR curve for the 8x8 fuel in Figure 3.2.4-1 is re-drawn to correct a plotting error in order to.be consistent with the values shown.

Specification 5.3.1 is revised to generalize the description for all Cycle 4 fuel types.

The affected bases were revised to reflect the Techn! cal Specifications changes and to provide corresponding justification.

JUST!,F_ICATION:

i 1

MAPLHGR Limits i The MAPLHGR limits for previously loaded ANF fuel were established on a cycle-independent basis and remain applicable for Cycle 4. Single Loop Operation is discussed in the following section. A MAPLHGR limit for the l

new 8x8 fuel type is added to the Technical Specifications for Cycle 4.

The MAPLHGR limit for the new fuel type is determined u ng methods l

consistent with those used for fuel types introduced is*c the core for previous reloads. The MAPLHGR limit was established from the LHGR limits by dividing the ANF 8x8 LHGR limit by the exposure dependent maximum local l

l peaking factor. The MAPLHGR limit is consistent with the LHGR limit so l

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that at reduced power and/or reduced flow, the allowable LHGR will be limited by the product of the MAPFACp or MAPFAC f multipliers and the MAPLHGR limits.

Single Loop Operation MAPLHGR The MAPLHGR limit for Single Loop Operation (SLO) for the 8x8 fuel has been conservatively revised to bound Cycle 4 operation. The MAPLHGR for ANF fuel inserted during the first reload is bounded by the SLO MAPLHGR limits for exposures up to 28.5 GWd/MTV. This exposure is expected to be exceeded by the first ANF reload batch during Cycle 4. Accordingly, the Cycle 4 SLO MAPLPGR limit has been conservatively defined. This limit is the minimum of the MAPLHGR limits applicable during Cycle 4 for all Ox8 fuel types and the Cycle 3 SLO MAPLPGR limit. As in Cycle 3, the Cycle 4 off-rated SLO MAPLHGR operating limit for all 0x8 fuel types is determined l

f by multiplying the SLO MAPLHGR limit by the minimun of the SLO MAPFACf .

MAPFAC or 0.86. The SLO MAPFAC is based on the limiting MAPFAC f curve p f for GE fuel . The portion of this curve for MAPFACf values above 0.86 is deleted since 0.86 is the raximum allowable value during SLO.

(

I r

Flow Dependent Thermal Limits The flow dependent thermal limits, MCPR fand MAPFACf . were constructed based on ANF analyses for GGNS-1 while assuring adequate margin to limits following a flow runout event. An added conservatism to bound possible f

l variations in subsequent cycles was introduced (see attached report NES00-88-003). These linits are applicable for a full ANF core and were t

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confirmed by ANF for Cycle 4 (see attached report ANF-88-149). Each of the limits is determined for both the Loop Manual and the Non loop Manual modes of operation.

The Loop Manual mode of operation is the only mode in which the two recirculation loops are controlled independently. The most severe flow runout event in this mode involves the flow increase of one loop while the other loop is unaffected (i.e., recirculation flow control v31ve (FCV) position is unchanged). The initial and final core flow values for the one loop runout esent are provided in report NES00-88-003. The flow increases were determined conservatively to bound the expected increases in flow rates. Tlie flow increase as a result of the one loop runout event is smaller than 1he increase during the two loop runout event.

In the Non Loop Manual modes of operation, a single controller controls

! the position of both recirculation FCVs. The most severe flow runout event for the Non Loop Manual trodes of operation, is, therefore the two loop runout event. A conservative maximum core flow (110% of rated core flow) is used to bound the marimum achievable core flow for the limiting runout event.

I Power-Dependent MCpR Limit The power-dependent MCPR, MCPR p

, wl.s constructed using ANF methodology for a full ANT core. The MCPR above 40% of rated power is based on the p

generic ANF CRWE results for BWR-6. The Cycle 3 limit has been confirmed l

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at and below 40% of rated power and at 100% power. Analyses of the most limiting core-wide transients and local events confimed the MCPR p limit for use in Cycle 4 (see atached report ANF-88-149).

Lead Test Assemblies _

The insertion of four ANF 9x9-5 LTAs in non-limiting core locations is inconsequential to the behavior of the core, which includes a total of 800 fuel assemblies. Analyses were perfomed to assure that operating limits determined to apply to an all 8x8 core would be applicable to the LTAs.

The LTA design is mechanically and thermal-hydraulically compatible with the 8x8 fuel core. The thermal and mechanical performance of the LTA for the limiting events analyzed by ANF for Cycle 4 are bounded by the 8x8 ,

fuel performance. The MAPLHGR and LHGR limits (including limits for SLO) provide adequate margin to the requirements of 10CFR50.46 and the fuel mechanical design criteria, respectively. Additional margin is provided i by placing the LTAs in non-limiting locations. Results of specific l analyses are provided in ANF report ANF-88-149.

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