ML20024C240

Proposed Tech Spec Change Re Max Critical Power Ratio & Maphlgr Limits

ML20024C240
Person / Time
Site:	Quad Cities
Issue date:	07/05/1983
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20024C237	List: ML20024C236 ML20024C240 ML20024C248
References
6882N, NUDOCS 8307120438
Download: ML20024C240 (6)

Text

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I ATTACHMENT 1 Proposed Change to OPR-30 Pages 3.5/4.5-10 3.6/4.6-4 6882N B307120438 830705 PDR ADOCK 05000265 P PDR

Quad Cities DPR-30 within the prescribed limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the r: actor shall be brought to the cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Surveillance and corresponding action shall_ continue until reactor operation is within the prescribed limits.

Maximum allowable LHGR for all 8X8 fuel types is 13.4 KW/ft.*

K. Minimum Critical Power Ratio (MCPR) K. Minimum Critical Power (MCPR)

During steady-state operation at rated The MCPR shall be determined daily during core flow, MCPR shall be greater than steady-state power operation above 25%

or equal to: of rated thermal power.

1.34for%ye60.73 secs 1.39 forJave 2 0.86 secs 0.385 Tave + 1.059 for 0.73< Tave 4 0.86 secs where 7 ave = mean 20% scram insertion time for all surveillance data from Specification 4.3.C which has been gene-rated in the current cycle.

For core flows other than rated, these nominal values of MCPR shall be increased by a factor l of kr where kr is as shown in Figure 3.5.2.

l If any time during operation it is determined by normal surveillance that the limiting value for MCPR is being exceeded, action shall be t initiated within 15 minutes.to restore operation to within the prescribed limits. If the steady-state MCPR is not returned to within the prescribed limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the reactor shall be brought to the cold shutdown condition eithin 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Surveillance and corresponding

-tetion shall continue until reactor operation is within the prescribed limits.

• For the purpose of the end-of-cycle 6 Barrier Fuel Ramp Test, the steady-state LHGR for the Barrier Ramp Cell fuel may exceed the maximum allowable LHGR identified in Technical l

Specification 3.5.J by no more than 10 percent (14.7 KW/ft), effective from initiation of i the test until the end of operation Cycle 6 shutdown.

l Amendment No. 51, 69, 79 3.5/4.5-10 l 6312N l

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Amendment No. 54

T l

i ATTACHMENT 2 Discussion of Quad Cities Unit 2 Reload 6, Cycle 7 ,

(Q2R6C7) Proposed Technical Specifications Changes i-i

! . _ The purpose of the proposed Q2R6C7 changes is to update the .

1 Technical Specifications to reflect:

a) reduction of the MCPR operating limit to 1.34 to provide additional operating margin afforded by the Q2R6C7 reload e analysns.

a b) applicability 'of existing non-barrier fuel MAPLHGR limits to the Q2C7 barrier reload fuel (type BP80RB265H)

Both'of these changes are specifically addressed in the following sections.

• MCPR-Limits 1

l' The current Quad Cities. Unit 2 Techncial Specifications establish an ODYN " option B" MCPR operating limit of 1.37. The option B approach f takes credit ror actual scram time performance relative to the Technical i Specifications surveillance limits and therefore requires a scram time  ;

i conformance surveillance. Exceeding the surveillance criterion (TB)

invokes a MCPR penalty-in the form of a linearly _ increasing limit between

! the option B value (currently 1.37) and the option A value (1.42). The

- Q2R6C7 reload analysis (see Attachment 4 section 12) establish a Cycle 7 i' option B MCPR limit of 1.32 (which bounds the results for all Cycle 7 ,

fuel types) based on the load rejection without bypass event. Full reduc-

' tion of the Technical Specifications to the allowable 1.32 MCPR value i- ,

could require. future Technical Specification changes if subsequent reload i require slightly higher MCPR limits. Therefore, in order to simultane-i ously preserve the option to review future reloads under 10 CFR 50.59 and l improve plant operating margin to MCPR, a value of 1.34 is proposed for the Technical Specifications option B MCPR limit. Based on the option A value provided in Attachment 4 (increased by 0.02 for the above reason),

the linearly increasing MCPR penalty was. determined and included in the proposed specification change.

i The reduction in'the operating MCPR limit calculated by GE (from

. 1.37 to 1.32 for ODYN option B) is largely a result'of improved i

l assumptions in analyses assumed that the recirculation pump M/G set which

~

- is driven from the generator would transfer to off-site power in 0.42 seconds. This' transfer actually~ occurs in'less than 0.1 seconds,which

- precludes recirculation pump run-up during the postulated load reject without bypass event. f 5

4 4

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2-MAPLHGR Limits Reference (c) contains the previously approved ECCS analysis for Quad Cities Units 1 and 2 and continues to serve as the basis for the MAPLHGR limits. The proposed Technical Specifications change (Attachment

1) revises the MAPLHGR curve for fuel type P8DRB265H to also apply to the Cycle 7 barrier reload fuel (fuel type BP80RB265H) which exhibits the sace MAPLHGR limit behavior as a function of exposure. The application of non-barrier MAPLHGR limits to barrier fuel of the same nuclear design was confirmed by GE and has been previously approved by the NRC (see Technical Specification 3.5-1 sheet 2). This label change is therefore administrative and in our assessment is not required for Q2C7 operation since there is a precedent from the previous reload that the non-barrier MPALHGR limits apply to barrier fuel. However, to avoid confusion, the label change is being formally submitted.

Errata and Addenda sheets for the Reference 4 LOCA analysis are included in Attachment 5 for your' review.

6882N

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4 ATTACHMENT 3 SIGNIFICANT HAZARDS CONSIDERATION Commonwealth Edison has evaluated the prope me. 1 2canical Specifi-cation amendment and determined that it does not represent a significant hazards consideration. Based on the criteria for defining a significant hazards consideration established in 10 CFR 50.92(e), operation of Quad Cities Unit 2 in accordance with the proposed amendments will not:

1) involve a significant increase in the. probability or consequences of an accident previously evaluated because:

a) the amendments involve restrictions on the reactor power distribution during normal operaton which of itself cannot initiate an accident and therefore does not increase the probability of an accident and b) these restrictions on power distribution are based on a reanalysis or re-evaluation of operating transients and accidents in accordance with NRC approved methods and are specifically provided to ensure that the consequences of transients or accidents (LOCA) during Q2C7 remain within the existing safety limits and accident criterie established for Quad Cities.

2) create the possibility of a new or different kind of accident from any accident previously evaluated for the same reason as (1)a. above and

3) involve a significant reduction in the margin of safety since the amendments are specifically intended to ensure that the MCPR Fuel Cladding Integrity Safety Limit and the 10 CFR 50.46 ECCS criteria continue to be protected during Cycle 7 operation.

In consideration of the above, Commonwealth Edison expects that NRC approval of these amendments should not be predicated on satisfactory l

resolutior, of public comments or intervention as provided for by 10 CFR 50.91(a)(4).

l 6882N

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