ML20207N009

Discusses 860620 Application for Amends to Licenses DPR-57 & NPF-5,revising Tech Specs Re single-loop Operation & Jet Pump Surveillance.Revised Unit 1 Tech Specs Bases Page 3.6-22 Encl

ML20207N009
Person / Time
Site:	Hatch
Issue date:	01/02/1987
From:	Gucwa L GEORGIA POWER CO.
To:	Muller D Office of Nuclear Reactor Regulation
References
SL-1717, TAC-61900, TAC-61901, NUDOCS 8701130384
Download: ML20207N009 (3)

Text

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Georgia Fbwer Company 333 Picdmont Avenue Atlanta, Georgia 30308

- Telephono 404 526-6526 Mailing Address:

Fbst Office Box 4545 Atlanta, Georgia 30302 g Georgia Power L T. Gucwa the sauthern electic system Manager Nuclear Safety and Licensing SL-1717 r 33C January 2,1987 Director of Nuclear Reactor Regulation Attention: Mr. D. Muller, Project Director BWR Project Directorate No. 2 Division of Boiling Water Reactor Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:

SINGLE-LOOP OPERATION AND JET PUMP SURVEILLANCE SUPPLEMENTAL INFORMATION Gentlemen:

By letter dated June 20, 1986, Georgia Power Company requested that amendments be incorporated into the Technical Specifications for Plant Hatch Units 1 and 2 regarding single i ecirculation loop operation and jet pump surveillance. The (proposed) revised Technical Specifications pages contained references to " General Electric Standard Application for Reactor Fuel (Supplement for United States)," NEDE-240ll-P-A. This reference appeared on Technical Specification pages 1.1-8, 1.1-17, and 3.11-6 for Unit 1 and on pages B 2-13 and B 3/4 2-6 for Unit 2. %e specific revision was not delineated in the Technical Specification ;

because of General Electric's frequent updating of the GESTAR documen:

In Georgia Power Company's submittal addressing single-loop operation and jet pump surveillance, all references to the GESTAR document were based upon NEDE-24011-P-A-8.

g 0 000$y PDR I l

Georgia Power d Director of Nuclear Reactor Regulation Attention: Mr. D. Muller, Project Director BWR Project Directorate No. 2 January 2,1987 Page Two Also, per your verbal request, we have enclosed a revised Unit 1 Technical Specifications Bases page 3.6-22. If you have any questions in this regard, please contact this office at any time.

Sincerely,

$7~4- e -

L. T. Gucwa GKM/lc Enclosure c: Georgia Power Company U. S. Nuclear Regulatory Commission Mr. J. P. O'Reilly Dr. J. N. Grace, Regional Administrator Mr. J. T. Beckham, Jr. Mr. P. Holmes-Ray, Senior Resident Mr. H. C. Nix, Jr. Inspector - Hatch GO-NORMS 0983C 700775

.e ,

SASES FOR LIMITING CONOITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3.6.I. Jet Punos (Continued)

A nozzle-riser system failure could also generate the coincident failure of a jet pump body; however, the converse is not true. The lack of any substantial stress in the jet pump body makes failure impossible without an initial nozzle riser system failure.

One of the acceptable procedures for jet pump surveillance, identified in NUREG/CR-3025, Reference 2, was adopted for Hatch Unit 1. The surveillance

' is performed to verify that neither of the following conditions occur:

(a) The Recirculation Pump Flow / Speed Ratio deviates by more than 55 from the normal range, or (b) The Jet Pump Loop Flow / Speed Ratio deviates by more than 55 from the normal range.

If either criterion is failed, then the procedure calls for comparing either the individual jet pump flow or individual jet pump diffuser to lower plenum differential pressures to the criteria of the Limiting Conditions for Operation (LCO). If the LCD criteria are not satisfied and pump speed is less than 605 of rated, it may be necessary to 2

increase pump speed to above 605 of rated and repeat the measurements before declaring a jet pump inoperable. In this case, it is reconnended that close monitoring and increased recirculation pump 1

speed should be performed only if the criteria are exceeded by an amount to be determined from previous plant operating experience.

! 3.6.J. Recirculation Systes

! Operation with a single reactor coolant system recirculation pump is allowed, provided that adjustments to the flow referenced scram and APRM rod block setpoints, MCPR cladding integrity Safety Limit, MCPR Operating Limit, and MAPLHGR limit are made. An evaluation of the performance of the ECCS i with single-loop operation has been performed and determined to be acceptable, Reference 4. Based on this Reference, a MAPLHGR factor of 0.75 is applied to the specifications, Figure 3.11-1 (Sheet 6). To account for increased uncertainties in the total core flow and TIP readings when operating with a single recirculation loop, a 0.01 increase is applied to the MCPR cladding integrity Safety Limit and MCPR Operating Limit over the comparable two-loop values. The flow referenced simulated thermal power scram and rod block setpoints for single-recirculation-loop operation is reduced by the amount of maw, where e is the flow reference slope for the rod block monitor and aW is the largest difference between two-loop and single-loop effective drive flow when the active loop indicated flow is the same. This adjustment is necessary to preserve the original relationship between the rod block and actual offective drive flow.

When restarting an idle pump, the discharge valve of the idle loop is required to remain closed until the speed of the faster pump is below 50% of its rated speed to provide assurance that when going from one- to two-loop ,

operations, excessive vibration of the jet pump risers will not occur.  ;

The possibility of experiencing limit cycle oscillations during single-loop operation is precidded by restricting the core flow to greater than or equal to 455 of rated core flow when core power is greater than the 805 rod line. '

This requirement is based on General Electric's reconnendations contained in SIL 380. Revisien 1, which defines the region where the limit cycle oscillations are more likely to occur.

HATCH - UNIT 1 3.6-22 Proposed TS/0025q/196

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