Text

Proposed TS 3.9.3 Re Refueling Operations Decay Time
	ML17332A413
Person / Time
Site:	Cook
Issue date:	11/16/1994
From:	; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML17332A412	List: ML17332A411; ML17332A413; ML17332A414;
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	NUDOCS 9411220358
	Download: ML17332A413 (29)
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ATTACHMENT 1 TO AEP:NRC:1202 10 CFR 50.92 ANALYSIS FOR CHANGES TO THE DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATIONS

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0 ATTACHMENT 1 TO AEP:NRC:1202 Page 1 1.0 ECTIO 0 BE CHANG

1. Technical Specification (T/S) 3.9.3

2. T/S Figure 5.6-1, "Normal Storage Pattern (Mixed Three Zone)."

3. T/S Figure 5.6-2, "Interim Storage Pattern (Checkerboard)."

2.0 E 0 C GES We are proposing to change T/S 3.9.3 to allow start of core offload 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months after core subcriticality.

2. Changes to Figure 5.6-1 are intended to correctly identify the number of region 1, 2, and 3 cells in the Normal Storage Pattern (Mixed Three Zona).

3. Changes to Figure 5.6-2 are intended to correctly identify the number of region 1, 2 and 3 cells in the Interim Storage Pattern (Checkerboard).

3.0 C GES R U S ED We are proposing to make the following changes to the Unit 1 and Unit 2 T/Ss (1-3) and commitments in AEP:NRC:1146 (4).

¹1 The amount of time the reactor must be subcritical before movement of irradiated fuel is decreased from 168 hours0.00194 days 0.0467 hours 2.777778e-4 weeks 6.3924e-5 months to 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months .

¹2 The number of region 1, 2 and 3 cells in Figure 5.6-1 is correctly changed from 504, 1415, 1694 to 504, 1439, 1670, respectively.

¹3 The number of region 2 and 3 cells in Figure 5.6-2 is correctly changed from 1415 and 1379 to 1439 and 1355, respectively.

Clarifications are made with respect to our spent nuclear fuel pool storage rack boral poison surveillance program commitments.

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ATTACHMENT 1 TO AEP:NRC:1202 Page 2 4.0 ~DCU~SS 0 echn ca S eci cat ion 3 9 3 Bases T/S 3.9.3 ensures sufficient resident time for the fuel in the core after subcriticality to allow for decay of short lived fission products. This decay time is a key input in to the spent fu'e1~.-.pool thermal hydraulic calculati'ons as it allows the fuel to cool off prior to placement into the pool. This cool off period ensures that design basis criteria are met for bulk pool temperature and concrete temperatures under worst case scenario.

Just i at on o Pro osed Tec cal ec f caC o an

¹1 Attachment 2 to this letter contains an analysis performed by Holtec International on behalf of I&M. This analysis reviews the impact of the proposed T/S change Chat reduces the time constraint imposed on movement of irradiated fuel.

The analysis concludes that the initiation of core offload after gust 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months of subcriticality with a lake temperature of less than or equal to 90 F, will not cause bulk pool water, fuel rod clad, or concrete temperatures around the pool to be at unacceptably high levels.

¹2 The changes to Figure 5.6-1 are editorial in nature.

¹3 The changes to Figure 5.6-2 are editorial in nature.

¹4 Clarification is given to the spent nuclear fuel pool storage rack boral poison surveillance program.

5.0 0 S GNIFIC S CONS DERATION DET N T 0 We have evaluated the proposed T/S, editorial and clarification changes and have determined that they do not represent a significant hazards consideration based on the criteria established in 10 CFR 50.92(c). Operation of Cook Nuclear Plant in accordance with the proposed amendment will not:

(1) olve a s i cant c ease the obab se ue c o acc de t e ous eva ted Although one of the proposed changes results in initiation of core offload earlier after subcriticality than is currently allowed, it does not increase the probability or consequences of an accident previously evaluated. The bulk pool water temperatures, fuel rod clad temperatures, and pool wall concrete temperatures will be

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ATTACHMENT 1 TO AEP'NRC:1202 Page 3 within acceptable limits as shown in Attachment 2. In addition, the subject change will not result in an uncontrolled release of radiation to the environment and will not initiate an accident.

The remaining changes are editorial in nature and have no affect on probability or consequences of a postulated accident.

(2) cate t e o s a ew di fe e d o acc de t a acc de t evious eva uated As previously stated, the earlier fuel movement change will not result in bulk pool water, fuel rod clad, or concrete temperatures which would initiate bulk pool boiling, challenge fuel rod integrity or jeopardize the structural integrity of the pool.

This change will also have no impact on the criticality, structural, seismic, or dropped assembly accident analysis previously performed and accepted by the NRC. Consequently, the proposed T/S change does not create the possibility of a new or different kind of accident from any previously analyzed. The remaining changes have no affect on nature or probability of a postulated accident.

(3) nvolve a si ificant reduction in a mar in of safe The proposed change for earlier fuel movement will not result in bulk pool water temperatures, fuel rod clad temperatures or

'concrete temperatures which would initiate bulk pool boiling, challenge fuel rod integrity or jeopardize the structural integrity of the pool. This proposed change will not affect the results of any other analysis associated with the spent fuel p'ool.

It is, therefore, concluded that this change poses no significant reduction in a margin of safety. The remaining changes have no affect on the nature or probability of a postulated accident.

6.0 PE G S P OPOSALS MPACTING IS SUBMITTA There are no other T/S proposals under review that impact this submittal.

ATTACHMENT 2 TO AEP:NRC:1202 SAFETY ANALYSIS PERFORMED BY HOLTEC INTERNATIONAL

ATTACHMENT 3 TO AEP NRC:1202 EXISTING TECHNICAL SPECIFICATIONS FOR DONALD C. COOK NUCLEAR PLANT UNITS 1 6 2 MARKED TO REFLECT PROPOSED CHANGES

REFUELING OPERATIONS DECAY TIAE LIMITING CONDITION FOR OPERATION 1OD 3.9.3 The reactor shall be subcritical for at least+&8.hours.

APPLICABILITY: During movement of irradiated fuel in the reactor pressure

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vessel.

ACTION:

100 Lich the reactor subcritical for less than +&8 hours, suspend *11 operations involving movement of irradiated fuel in the reactor pressure vessel. The provisions of Specification 3.0.3 are not applicable, SURVEILLANCE REOUIR~~:"VVS 4.9.3,~e reactor shall be determined to have been subcritical for *t least~ hours by verification of the date and time of subcriticality prior to movement of irradiated fuel in the reactor pressure vessel.

COOK NUCLEAR PLANT - UNIT 1 3/4 9-3 AMENDMENT NO.

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REFUELINC OPHVLTIONS DECAY TINE LINITIVC CONDITIOiN POR OPERATION iao 3,9.3 The reactor shall be subcritical for at least~ hours.

APPLICASILITY: During, movement of irradiated fuel in the reactor pressure vessel,

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Pith the reactor subcritical for less than ~

los hours, suspend all operations involving movement of irradiated fuel in the reactor pressure t

vessel. The provisions of Specification 3.0.3 are not applicable.

SURUEILLAHCE RE UIR~ tEVNTS 4.9.3 The reactor shall be determined to have been subcritical for at least 4$ 'ours by verification of the date and time of subcriticality prior to movement of irradiated fuel in the reactor pressure vessel; t

COOK NUCLEAR PLANT - UNIT 2 3/4 9-3 AKENDMENT NO.~R

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Flic% 5,6-1: Normal Storage Par."em (Aired Three Zone)

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Pique'e 5.6-2: Int:crim Scarabee Pactern {Checkerboard)

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ATTARlMENT 4 TO AEP:NRC:1202 PROPOSED TECHNICAL SPECIFICATIONS FOR DONALD C. COOK NUCLEAR PLANT UNITS 1 & 2

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GO TOS DEC~~IME L MI G CONDITIO FO 0 ERAT 0 3.9.3 The reactor shall be subcritica1'"=for..at least 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months .

vessel.

Pith the reactor subcritical for less than 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months , suspend all operations involving movement of irradiated fuel in the reactor pressure vessel. The provisions of Specification 3.0.3 are not applicable. ll SURVEILLANCE RE UI ENTS 4.9.3 The reactor shall be determined to have been subcritical for at least 100

'ours by verification of the date and time of subcriticality prior to movement

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of irradiated fuel in the reactor pressure vessel.

COOK NUCLEAR PLANT - UNIT 1 3/4 9-3 AMENDMENT NO. 169

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REFUELI G OPERATIONS 1H~C'GHK LIM T G CONDI ON R 0 ERA ION 3.9.3 The reactor shall be subcritical for at least 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months ;<""<---

V vessel.

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With the reactor subcritical for less than 100 hours, suspend all operations involving movement of irradiated fuel in the reactor pressure vessel. The provisions of Specification 3.0.3 are not applicable.

S VEIL CE RE UI 4.9.3 The reactor shall be determined to have been subcritical for at least 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months by verification of the date and time of subcriticality prior to movement of irradiated fuel in the reactor pressure vessel.

COOK NUCLEAR PLANT - UNIT 2 3/4 9-3 AMENDMENT NO. 152

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