ML20197H517

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Proposed Tech Specs Section 2.1.1.2,deleting Footnote Which Specifies That SLMCPRs Are for Cycle 18 Only & TS Section 5.6.5.b.2
ML20197H517
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 12/04/1998
From:
SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20197H513 List:
References
NUDOCS 9812140124
Download: ML20197H517 (8)
v • d • e


Text

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Enclosure 3 Edwin I. Hatch Nuclear Plant Request to Revise Technical Specifications:

Safety Limit Minimum Critical Power Ratios (SLMCPRs)

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5.0-19 Replace Unit 2 i

Remove Pane Instruction 1

5.0-19 Replace  !

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HL-5698 E3-1

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SLs i 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 React >r Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core i flow < 10% rated core flow: l THERMAL POWER shall be s 25% RTP.

2.1.1.2 With the reactor steam dome pressure a: 785 psig and core flow a: 10% rated core flow:  ;

MCPR shall be 2: 1.10 for two recirculation loop operation or 2: 1.12 for single recirculation loop operation. l 2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel .

2.1.2 Reactor Coolant System (RCS) Pressure SL Reactor steam dome pressure shall be s 1325 psig.

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2.2 SL Violations i l

With any SL violation, the following actions shall be completed: l 2.2.1 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, notify the NRC Operations Center, in accordance with 10 CFR 50.72.

2.2.2 Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

2.2.2.1 Restore compliance with all SLs; and 2.2.2.2 Insert all insertable control rods.

2.2.3 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the plant manager, the corporate executive responsible for overall plant nuclear safety, and the offsite review committee.

(continued)

HATCH UNIT 1 2.0-1 LDCR NO.98-216

Reporting Requirements 5.6

! 5.6 Reporting Requirements (continued) l 5.6.5 CORE OPERATING LIMITS REPORT (COLR) i

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
1) The Average Planar Linear Heat Generation Rate for Specification 3.2.1.
2) The Minimum Critical Power Ratio for Specification 3.2.2.
b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in NEDE-240ll-P-A,

" General Electric Standard Application for Reactor Fuel,"

(applicable amendment specified in the COLR).

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits and accident analysis limits) of the safety analysis are met.
d. The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

(continued)

HATCH UNIT 1 5.0-19 LCDR N0.98-216

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Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:
1) The Average Planar Linear Heat Generation Rate for Specification 3.2.1.
2) The Minimum Critical Power Ratio for Specification 3.2.2.
b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in NEDE-240ll-P-A,

" General Electric Standard Application for Reactor Fuel,"

(applicable amendment specified in the COLR).

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits and accident analysis limits) of the safety analysis are met.
d. The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

(continued)

HATCH UNIT 2 5.0-19 LDCR N0.98-216

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I Enclosure 4 -

!. Edwin I. Hatch Nuclear Plant Request to Revise Technical Specifications:

l Safety Limit Minimum Critical Power Ratios (SLMCPRs)

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. SLs 2.0 0 2.0 S,AFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core  :

flow < 10% rated core flow-l THERMAL POWER shall be s 25% RTP.

2.1.1.2 With the reactor steam dome pressure d 785 psig and core flow a 10% rated core flow: )

MCPR shall be 21.10 for two recirculation loop operation -

or 21.12 for single recirculation loop operationP 0- 1 l

2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.

2.1.2 11eactor Coolant System (RCS) Pressure SL l Rt. actor steam dome pressure shall be s 1325 psig.

'50 specif 4Ad limits-we for Cycle 18 erly. J l l

2.2 SL Violations With any SL violation, the following actions shall be completed:

2.2.1 Within I hour, notify the NRC Operations Center, in accordance with 10 CFR 50.72.

2.2.2 Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

2.2.2.1 Restore compliance with all SLs; and 2.2.2.2 Insert all insertabie control rods.

2.2.3 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the plant manager, the corporate executive responsible for overall plant nuclear safety, an6 the offsite review committee.

(continued)

HATCH UNIT 1 2.0-1 Amendment No. 209

Reporting Requirements

. 5.6  ;

1 O 5.6 Reporting Requirements V- -

(continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR)  !

a. Core operating limits shall be established prior to each  !

reload cycle, or prior to any remaining portion of a reload .

cycle, and shall be documented in the COLR for the l following: I

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1) The Average Planar Linear Heat Generation Rate for p' ,

Specification 3.2.1. q

2) The Minimum Critical Power Ratio for Specification d 3.2.2. 2 i

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b. The analytical methods used to determine the core operating i limits shall be those previously reviewed and approved by the NRC, specifically those described in-the fell ing lj

_d o e n=n a te : --C. __

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-F) DE-24011-P-A, " General Electric Standard Application for Reactor Fuel," (applicable amendment specified in )

the COLR). 1 r

O 2) "S:fety Evaluatier by th Office of tele:r Re::ter I WN.

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c. The core operating limits shall be determined such that all  !

applicable limits (e.g., fuel thermal mechanical limits,  !

core thermal hydraulic limits, Emergency Core Cooling i Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits and accident analysis limits) of the safety analysis are met.  ;

i

d. The COLR, including any mid-cycle revisions or supplements, i shall be provided upon issuance for each reload cycle to the l NRC. {

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' (continued)

HATCH UNIT 1 5.0-19 Amendment No. 210

I i

. . Reporting Requirements

} , 5.6 5.6 Reporting Requirements (continued) l 5.6.5 CORE OPERATING LIMITS REP 0FT (COLR) s l

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload i cycle, and shall be documented in the COLR for the following: l c
1) The Average Planar Linear Heat Generation Rate for ( ;7 Specification 3.2.1.
2) The Minimum Critical Power Ratio for Specification f 3.2.2.

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b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described itythe fell Wing-der. 45. '- _- -

4}4 CNEDE-24011-P-A, " General Electric Standard Application for Reactor Fuel," (applicable amendment specified in I

the COLR).

' 2) "Saf+ty-4vah:: tion by th Offic: Of N :10:r Re::ter

( -Regulation Supporting ? :nda nt N :. 151 ::d 99 te- '

{egilityjpegng-tdeenses OPR-57 and NPP-5," dot;d-v.im.., . . , . . , _ .

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits and accident analysis limits) of the safety analysis are met,
d. The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

(continued)

HATCH UNIT 2 5.0-19 Amendment No. 151 2

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