ML20062H827

Application for Amend of License DPR-29,changing Tech Specs to Support Review of Future Reloads.Cycle 6 Operation Is Scheduled to Begin 801123.Class III Fee Encl

ML20062H827
Person / Time
Site:	Quad Cities
Issue date:	09/02/1980
From:	Janecek R COMMONWEALTH EDISON CO.
To:
Shared Package
ML20062H829	List: ML20062H827 ML20062H831
References
NUDOCS 8009080338
Download: ML20062H827 (4)

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Commonwezith Edison

@ One First National Plaza, Chicago, I;;ino Address Reply to: Post Office Box 767 Chicago, Illinois 60690 paPL I c A TE September 2, 1980 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 .

Subject:

Quad Cities Station Unit 1 Proposed Amendment to Appendix A, Technical Specification, to Facility Operating License DPR-29 to Implement 10 CFR 50.59 Reload Licensing NRC Docket No. 50-254 References (a): J. F. Quirk letter to Olan D. Parr,

" General Electric Licensing Topical Report, NEDE-240ll-P-A, ' Generic Reload Fuel Application, Appendix D, Second Submittal'", dated February 28, 1979.

(b): C. Reed letter to Director of Nuclear Reactor Regulation dated August 30, 1979.

(c): D. L. Peoples letter to Director of Nuclear Reactor Regulation dated March 19, 1980.

Dear Sir:

Pursuant to 10 CFR 50.59, Commonwealth Edison proposes to amend Appendix A, Technical Specifications, to Facility Operating License DPR-29 to support the review of future reloads for Quad Cities Unit 1 by Commonwealth Edison in accordance with the provisions of 10 CFR 50.59. These changes are identified in Enclosure 1 and are based, in part, on plant analyses summarized in the " Loss of Coolant Accident Analysis Report for Dresden Units 2, 3 and Quad Cities Units 1, 2 Nuclear Power Stations," NEDO 24146A, 79NLD273, April, 1979 and Errata and Addenda No. 2 dated December, 1979, submitted in References (b) and (c).

The significant changes to the Technical Specifications include:

1. A generalization of the MCPR Safety Limit. As revised, the numerical value of 1.07 appears only on page 1.1/2.1-1 and is referred to elsewhere as the MCPR Fuel Cladding Integrity Safety Limit. With the introduction of retrofit fuel into Quad Cities Unit 1 in the Spring of 1979, the value of 1.07 is the current Safety Limit MCPR for Cycle 5 operation. .

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2. The Rod Drop Accident figure of merit has been changed from 1.3% AK to 280 cal /gm. This is a consequence of rod worths slightly less than 1.3% AK resulting in a peak fuel clad enthalpy of 280 cal /gm for some local peaking conditions. Similar revisions have previously been reviewed and approved for the other Edison large BWR's.

3. NEDO 24146A contains MAPLHGR limits for various retrofit fuel designs. These have been included in the proposed 10 CFR 50.59 Technical Specification changes to avoid later additions should these fuel designs become part of future core reload strategies. Extended MAPLHGR curves are also provided for the 8D250 and 8D262 fuel types. These proposed changes were previously submitted by Reference (c), but have not been approved and should be included in this review since they are required for the upcoming cycle. The review of these changes for Quad Cities Unit I should now be excluded from the review of Reference (c).

NEDO 24146A assumes only 156 bundles with drilled lower tie plates. Quad Cities Unit 1 Cycle 6 will utilize 416 retrofit 8X8 fuel bundles. Because the drilled lower tie plates of the retrofit fuel provide improved reflooding characteristics, the MAPLHGR limits presented in NEDO 24146A remain conservative for Cycle 6.

4. Reference to the limiting total peaking factor (LTPF) has been eliminated and replaced with reference to the maximum fraction of limiting power density (MFLPD) for adjustment of the APRM flux scram and rod block trip settings. This proposed change eliminates the need for different LTPFs for dif ferent fuel types as a consequence of dif ferent bundle heat transfer areas, while providing the same degree of protection (with respect to reduction of the trip settings). Therefore, the trip settings for the APRM scram and rod blocks will be reduced by FRP/MFLPD whenever the MFLPD exceeds the FRP (fraction of rated power). This ratio is equivalent to the ratio of LTPF to TPF (total peaking factor), i.e.

LTPF DLHGR/RCTP/K DLHGR CTP TPF = LHGR/CTP/K = LHGR

• RCTP

= 1 FRP MFLPD

• Where: DLHGR = Design Limit LHGR RCTP = Rated Core Thermal Power K = Constant

3-Also, the proposed Technical Specifications provide for increasing the APRM gains in lieu of an actual reduction in APRM trip set points whenever the MFLPD exceeds the FRP. This method establishes an initial APRM signal closer to the flow-biased setpoints, and thus has the same effect as reducing the actual scram and rod block setpoints. For consistency with the LHGR surveillance requirement and the Standardized Technical Specifications, the proposed changes also require that the FRP/MFLPD multiplier be applicable only above 25% rated thermal power.

5. The " Generic Reload Fuel Application", NEDE-24011-P-A, documents the fuel designs, methods, evaluations, codes, generic criteria, test results, and assumptions which are utilized in the reload licensing analyses. It has been referenced whenever appropriate in the proposed changes (e.g. to replace outdated references and discussions).

6. The limiting safety system bases for the APRM red block trip setting have been clarified to indicate that the setting provides protection against grossly exceeding the MCPR Fuel Cladding Integrity Safety Limit. Adequate local protection from a rod withdrawal error is provide by the RBM system alone. Previous wording did not cleal /

distinguish the functions of the two systems.

7. The uppe'r limit of the reactor protection system (RPS) delay time has been reduced from 100 to 50 msec (time from opening of the sensor contact up to and including the opening of the trip actuator contacts). This change stems from an inconsistency which has existed between the Technical Specification value of 100 msec and the 50 msec value assumed by General Electric in the licensing analyses. General Electric has confirmed that the Edison proc lures for determining RPS delay time are consistent with their use/ definition of a 50 msec RPS delay time in the licensing analyses.

The licensing analyses are also based on a value of 290 msec for the time the neutron sensor reaches the setpoint to the start of control rod motion. The value of 390 msec currently quoted in the Quad Cities Unit 1 Technical Specifications is inconsistent with this value, and is therefore revised.

The proposed changes of Enclosure 1 have received on-site and off-site review and approval.

Pursuant to 10 CFR 120, Commonwealth Edison has determined that the proposed amendment is Class III. As such, a fee remittance in the amount of $4,000.00 has'been enclosed.

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For purposes of your schedule, Cycle 6 operation, which l requires approval of these proposed changes, is scheduled to begin on November :23, 1980. l t

i Please address any questions concerning this matter to l this office.  ;

Three'(3) signed originals'and thirty-seven (37) copies of j this transmittal are provided for your use. (

1 Very truly yours,  ;

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Robert F. Janecek  !

Nuclear Licensing Administrator Boiling Water Reactors {

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Enclosure l

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SUBSCRIBED and SWORN to beforg me this d on day I of & .e W 8 9 u -.

, 1980 I 6eu Notary Public I

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