ML20080P620

Proposed Changes to Tech Specs Re MAPLHGR Curve Design for Core Reconstitution

ML20080P620
Person / Time
Site:	Hatch
Issue date:	09/29/1983
From:	GEORGIA POWER CO.
To:
Shared Package
ML20080P618	List: ML20080P616 ML20080P620
References
TAC-52448, NUDOCS 8310070280
Download: ML20080P620 (16)

Text

I ATTACHENT 1 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS GE Letter No. GGJ: 83-076 dated September 20, 1983 RE: MAPLHGR Curves for Hatch 1

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RECEIVED GEN ER AL @) ELECTRIC EA GEN.'

NUCLEAR ENERGY BUslNEss OPERATIONS GENERAL ELECTRIC COMPANY

• 175 CURTNER A'KNUE o SAN JOSE, CAUFORNIA 95195 September 20, 1983 cc: Georgia Power Company GGJ:83-076 L. T. Gucwa H. C. Nix Southern Company Services B. E. Hunt L. K. Mathews Mr. R. D. Baker Georgia Power Company P. O. Box 4545 Atlanta, GA 30302

Subject:

MAPLHGR Curves for Hatch 1

Dear Mr. Baker:

The purpose of this letter is to transmit the infomation you requested so that H2R1 (P8DRB284LA) and H2R2 (P80RB283) fuel types can be used in the Hatch 1 reactor.

The MAPLHGR Versus Exposure for the two fuel types are presented in Tables 1 and 2 attached hereto.

GE has evaluated these two fuel types and concluded that the attached curves conservatively bound their use in Hatch 1.

An Errata and Addenda Sheet to NED0-24086 will follow shortly.

Sincerely, G. G Jon s Senior Fuel Project Manager Hatch 1, 2 M/C 174; (408)925-1516 GGJ:lo Attachment

TABLE 1 MAPLHGR vs Exposure Fuel Type: P8DRB284LA Exposure MAPLHGR PCT 0xidation (mwd /t)

(kW/ft)

{ F)

Fraction 200 11.7 2189 0.034 1,000 11.8 2190 0.033 5,000 12.0 2198 0.033 10,000 12.1 2197 0.033 15,000 12.1 2198 0.033 20,000 12.0 2194 0.033 25,000 11.5 2130 0.026 30,000 10.8 2032

0. 01 9 35,000 10.1 1934

0. 01 4 40,000 9.5 1840 0.01 0 45,000 8.9 1758 0.007 TABLE 2 MAPLHGR vs Exposure Fuel Type: P8DRB283 200 11.30 2133 0.029 s

1,000 11.40 2134 0.028 5,000 11.90 2185 0.033 10,000 12.10 2195 0.033 15,000 12.10 2199 0.033 20,000 11.90 2184 0.032 25,000 11.30 2112 0.025 30,000 11.10 2061 0.021 35,000 10.50 1931 0.030 40,000 9.80 1878 0.017 45,000 9.20 1788 0.008 GGJ - 9/16/83

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ATTACHMENT 2 i

NRC DOCKET 50-321 OPERATING LICENSE DPR EDWIN I. HATCH NUCLEAR PLANT UNIT 1 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS i

Pursuant to 10 CFR 170.12 (c), Georgia Power Company has evaluated the attached proposed amendments to Operating License DPR-57 and has depermined that:

a.

The proposed amendment does not require evaluation of a new Safety 7

Analysis Report and rewrite of the facility license; i

b.

The proposed amendment does not require evaluation of'several' complex issues, involve ACRS review, or require an. environmental impact statement; c.

The proposed amendment dues not involve a complex issue or more than one environmental or safety issue; i

d.-

The proposed amendment consists of three changes namely, addition of l

MAPLHGR operating limits for. new fuel _ types, extension of MAPLHGR i

operating limits based on analysis, and an increase in the MCPR limit in order to cover contingencies.

These changes result from a core reconfiguration.

~e.

Therefore, the proposed change is a Class III amendment.

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IfilTING C0i1DITIONS FOR OPERATlCN SURVEILLAtiCE REqulREMRS 3.11 FUEL RODS 4.11 FUEL RODS Applicability Applicability The Limiting Conditions for Operation The Surveillance Requirements apply to the associated with the fuel rods apply to parameters which monitor the fuel rod those parameters which monitor the fuel operating conditions.

rod operating conditions.

Objective Objective The Objective of the Limiting Conditions The Objective of the Surveillance for Operation is to assure the performance requirements is to specify the type and of the fuel rods, frequency of surveillance to be applied to the fuel rods.

Specifications Specifications A. Average Planar Linear Heat A. Average Planar Linear Heat Generation Rate (APLHGR)

Generation Rate (APLHGR)

During power operation, the APLHGR for The APLHGR for each type of fuel as a each type of fuel as a function of average function of average planar exposure shall planar exposure shall not exceed the be determined daily during reactor limiting value shown in Figure 3.11-1, operation at 2 25% rated thermal power.

sheets 1 thru 5.

If at any time during operation it is determined by normal surveillance trat the limiting value for APLHGR is being exceeded, action shall be initiated within 15 minutes to restore operation to within the prescribed limits.

If the APLHGR is not returned to within the prescribed limits within two (2) hours, then reduce reactor power to less than 25% of rated thermal power l

within the next four (4) hours.

If the i

limiting condition for operation is restored prior to expiration of the j

specified time interval, then further progression to less than 25% of rated thermal power is not required.

1 l

B. Linear Heat Generation Rate B. Linear Heat Generation Rate (LHGR)

(LHGR)

During power operation, the LHGR as a The LHGR as function of core height shall function of core height shall not exceed be checked daily during reactor operation the limiting value shown in Figure 3.11-2 at 2 25% rated thermal power.

for 7 x 7 feel or the limiting value of l

i 13.4 kw/ft for 8 x 8/8 x 8R fuel.

If at any time during operation it is determined by normal surveillance that the limiting value for LHGR is being exceeded, action i

shall be initiated within 15 minutes to restore operation to within the prescribed l

limits.

If the Amendnent No. pi, pf,%, [

3.11-1

T.

BASES FOR LIMITIE CO@ITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

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3.11 FUEL ROOS A

Averade Planar ' Linear Heat Generation Rate (APLHGR)

This specification assures that the peak cladding temperature following the postulated design basis loss-of-coolant accident will not exceed the limit i

.specified in the 10 CFR SC, Appendix K, even considering the postulated effects of fuel pellet _ densification.

The peak cladding temperature following a postulated loss-of-coolant acci-dent is primarily a_ function of the average heat generation rate of all the rods of a fuel assembly at any axial location and is only dependent second-arily on the rod to rod power distribution within an assembly. Since expected local variations in power distribution within a fuel assembly affect i

the calculated peak clad temperature by less than + 200 F relative to the l

peak temperature for a typical fuel design, the liiiilt on the average linear heat generation rate is sufficient to assure that calculated temperatures are within the 10 CFR 50, Appendix K limit. The limiting value for APLHGR 4

is shown in Figures 3.11-1., sheets 1 thru 5.

l The calcualtional procedure used'to establish the APLHGR shown in Figures 3.11-1, sheets l~ thru 5 is based on a less-of-coolant accident analysis..

The analysis was performed using General Electric (GE) calculational models which are consistent with the requirements of Appendix K to 10 CFR 50. A i-complete discussion of each code employed'in the analysis is presented in l

Reference 1.

Olfferences in 'this analysis as compared to previous analyses performed with Reference 1 are: (1) The analyses assumes a fuel assembly planar power consistent with 102% of the MAPLHGR shown in Figure'3.ll.1; (2) Fission product decay is computed assuming an energy release rate of 200 MEV/ Fission;-(3) Pool boiling is. assumed after nucleate boiling is lost during the flow stagnation period; (4) The effects of core spray entrainment and counter-current flow limiting as described in Reference 2, are included in the reflooding calculations.

A list of the significant plant input parameters to the loss-of-coolant accident analysis is presented in Table 1 of NED0-21187 (3).

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ATTACHMENT 3 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS The proposed change to Technical Specifications (Appendix A to Operating License DPR-57) would be incorporated as follows:

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ATTACHE NT 4 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS Pursuant to the procedures and examples outlined in 10 CFR 50.92, Georgia Power Company has determined that this proposed amendment involves no significant hazards considerations since the reauested changes add Standard General Electric (GE) fuel types and revise certain operating limits based on analyses using GE standard methodology.

Consequently, existing margins are maintained.

Further, no new or different type of accident not previously evaluated is created nor do the, proposed changes involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed amendment can be broken into four issues for purposes of complying with 10 CFR.50.91 and for comparing these changes with examples of Amendments that are considered not ~ likely to involve significant hazards considerations published in Federal Register, April 6,1983, page 14870.

One change results from a nuclear reactor core reloading (example 11), namely, adding new MAPLHGR curves (Figures 3.11-1. Sheets 4 and 5) for fuel assemblies previously used in Plant Hatch Unit 2.

GE has evaluated their -use in Plant Hatch Unit 1 and, has determined that the' proposed MAPLHGR limits are bounding for use in Unit 1.

The second changc (pages. 3.11-1 and 3.11-3) is purely an administrative change (example 1) resulting from the need to accurately reference the new MAPLFOR curves.

A third change extends the MAPLHCR limits

beyond 30 Gwd/t based on analyses performed-by General Electric following approved methodology and reported in Reference 1 and Attachment 1 of this

, letter.

This change most.nearly fits example iv.

GPC understands that this relief has - been established by prior review. on.other docket's _ amendment applications.

The final change constitutes an additional limitation not presently included in the Technical Specification (example 11), namely, raising the MCPR operating limit to conservatively bound any core design resulting from this upcoming core reconstitution.

L

f ATTACHMENT 5 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1

, PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS

References:

1)

Letter, W.

A.

Widner(GPC) to Director, Nuclear Reactor Regulation (NRC) dated October 27, 1981 2)

Letter, J. F. Stolz (NRC) to J.

T.

Beckham (GPC), dated February 3, 1982 3)

Letter, R.

E.

Engel (GE) to D.

G.

Eisenhut (NRC),

" Extension of Emergency Core Ccoling System Performance Limits," dated May 6,-1981 4)

Letter, R.

E.

Engel (GE) to T.

A.

Ippolito (NRC),

" Additional Information Regarding Extension of Emergency Core Cooling System Performance Limits," dated May 28, 1981

_