ML20206J957

Application for Amends to Licenses DPR-57 & NPF-5,revising Tech Specs to Allow single-loop Operation & Jet Pump Surveillance,Per NUREG/CR-3052, BWR Jet Pump Assembly Failure. Fee Paid

ML20206J957
Person / Time
Site:	Hatch
Issue date:	06/20/1986
From:	Beckham J GEORGIA POWER CO.
To:	Muller D Office of Nuclear Reactor Regulation
Shared Package
ML20206J962	List: ML20206J957 ML20206K007
References
RTR-NUREG-CR-3052 0533C, 533C, SL-868, TAC-61900, TAC-61901, NUDOCS 8606270322
Download: ML20206J957 (15)

Text

Georgia Power Company 333 Piedmont Avenue Atlanta, Georgia 30308 Telephone 404 526 7020 Ma; ling Address:

Post Office Box 4545 Atlanta, Georgia 30302 h Georgia Power J. T. Beckham, Jr.  !"e southun e/wtre sprem Vice President and General Manager Nuclear Operat;ons SL-868 0533C June 20, 1986 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 i]ET PUMP SURVEILLANCE Gentlemer.:

In accordance with the provisions of 10 CFR 50.90, as required by 10 CFR 50.59(c)(1), Georgia Power Company (GPC) hereby proposes changes to the Edwin I. Hatch Units 1 and 2 Technical Specifications, Appendix A to Operating Licenses DPR-57 and NPF-5, respectively. The proposed revisions will allow for single-loop operation (SLO) and conformance to NUREG/CR-3052, " BWR Jet Pump Assembly Failure" (Reference 2).

The proposed change for SLO reflects the recommendations of General Electric Service Information Letter (SIL)-380, Revision 1 (Reference 1).

Corrections to the average power range monitor (APRM) scram and rod block equations, new MCPR Safety Limit and MAPLHGR limits, and a revised power-flow map will be required for continuous operation with a single recirculation pump. Incorporation of these changes will ensure that SLO will not be more limiting than two-loop operation with respect to the plant licensing bases.

Jet pump surveillance is performed routinely at the plant using administrative procedures in conformance with NUREG/CR-3052 As part of the long-term solution, the NUREG recommends that the Technical Specifications be revised to reflect this fact. This proposed change is consistent with the Technical Specifications recommendations of NUREG/CR-3052, I

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Georgia Powerkh Director of Nuclear Reactor Regulation Attention: Mr. D. Muller, Project Director BWR Project Directorate No. 2 June 20, 1986 Page Two In addition, the Hatch 1 and 2 Technical Specifications Bases sections were updated to include infonnation describing abnormal transient and accident analyses and MCPR methodologies. These updated sections are consistent with currently approved methods and the GE BWR/4 Standard Technical Specifications.

Enclosure 1 provides a detailed description and safety evaluation of the proposed revisions and the circumstances necessitating the revision request.

Enclosure 2 details the bases for our determination that the proposed revisions do not involve significant hazards considerations.

Enclosure 3 provides page change instructions for incorporating the proposed revisions. The proposed revised Technical Specifications pages follow Enclosure 3 Payment of filing fee is enclosed.

To allow time for procedure revision and orderly incorporation into copies of the Technical Specifications, we request that the proposed amendment, once approved by the NRC, be issued with an effective date to be no later than 60 days from the date of issuance of the amendment.

Pursuant to the requirements of 10 CFR 50.91, a copy of this letter and all applicable enclosures will be forwarded to Mr. J L. Ledbetter of the Environmental Protection Division of the Georgia Department of Natural Resources.

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Geoigia Power A Director of Nuclear Reactor Regulation Attention: Mr. D. Muller, Project Director BWR Project Directorate No. 2 June 20, 1986 Page Three Mr. J. T. Beckham, Jr. st'ates that he is Vice President of Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Company; and that to the best of his knowledge and belief, the facts set forth in this letter are true. ,

GEORGIA POWER COMPANY By: Lh- d. T. Beckham, Jr.

Sworn to and subscribed before me this 20th day of June 1986

_.No [ ed Notary Public NotwyMhe, cfayton County, Georg.a MyCommission Expires cec. 12.1983 Enclosure

• c; Geordia Power Company Nuclear Regulatory Commission Mr.s. P. O'Reilly Dr. J. N. Grace, Regional Administrator Mr. J. T. Beckham, Jr. Senior Resident Inspector Mr. H. C. Nix, Jr. <

G0-NORMS State of Georgia ,

Mr. J. L. Ledbetter

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Georgia Powerkh ENCLOSURE 1 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 dET PUMP SURVEILLANCE BASIS FOR CHANGE REQUEST Proposed Change 1:

This proposed change will introduce a new Safety Limit, Limiting Safety System Settings, Limiting Conditions for Operation (LCOs), and Surveillance Requirements in conjunction with single-l oop operation (SLO). Technical Specifications changes will include new MCPR Safety and Operating Limits, changes to the recirculation system LC0 and Surveillance Requirements, adjustments to the average power range monitor (APRM) flow-biased trip settings, a new MAPLHGR limit, and a revised power-flow map.

Background:

The present Hatch Technical Specifications allow power operation with a single reactor system recirculation pump for only a short time. This SLO proposal for Hatch Units 1 and 2 is specifically designed to address the abnormal transient and accident analyses so that continuous operation with one recirculation pump can be achieved. The evaluation of SLO, which

is documented in NED0-24205 (Reference 3), indicates that since the maximum power level when operating with single-loop is considerably less than the maximum power that can be attained from operation with both ,

recirculation pumps running, the abnormal transient analysis for the i two-loop operation is bounding. To conservatively account for the increased uncertainties in the _ total core flow and traversing incore probe (TIP) readings, a 0.01 increase is proposed for the MCPR Safety i Limit (which results in a 0.01 increase in the MCPR Operating Limit) when in SLO. The Technical Specifications APRM flow-biased rod block and simulated thermal power monitor (STPM) equations are corrected to preserve the original relationship between the reactor power and actual effective core flow when operating with a single loop.

To preclude concern regarding potential core- thermal hydraulic instability when operating with a single recirculation pump, the current Technical Specifications prohibit single-loop operation in the region l

identified in GE SIL-380 (Reference 1) where limit cycle oscillations are most likely to occur. The allowance for long-term single-loop operation,

, as proposed in this revision, must also comply with the requirements of Reference 1. This is stated in Reference 7 and also in the USNRC Safety I

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Georgia Powerkh ENCLOSURE 1 (Continued)

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 BASIS FOR CHANGE REQUEST Background (Continued):

Evaluations for Technical Specifications Amendment Number 105 for Hatch Unit 1 and Amendment Number 39 for Hatch Unit 2. To maintain consistency with the Reference 1 power-flow map guideline, this proposal includes a revision to the Technical Specifications power-flow map for single-loop operation. Additionally, plant procedures based on Reference 1 were implemented to detect and suppress limit cycle oscillations.

Basis:

The basis for allowing continuous operation with a single recirculation pump is an analysis which considers the effect of SLO on design basis transients and accidents, as well as consideration of the potential for limit cycle oscillations.

There are six categories of design basis accidents: l oss-of-cool ant, recirculation pump seizure, control rod drop, main steam line break, refueling, and fuel assembly loading. Excluding the first two categories, all two-loop operation limits are conservatively applicable for SLO. (See Reference 4, NEDE-24011-P-A. ) For the loss-of-coolant accident analyses, an SLO analysis using NED0-20566-2 (Reference 5) models and assumptions was performed for each Hatch unit. Using this method, SAFE /REFLOOD computer code runs were made for the full spectrum of recirculation line break sizes for both suction and discharge side breaks. Because the core uncovery and reflood times for the single-loop analysis are similar to the two-loop analysis, the methodology presented in Section II. A.7.4.2 of NED0-20566-2 applies. Therefore, the MAPLHGR curves for two-l oop operation currently applied to each unit were modified by derived reduction factors and will be used during continuous operation with a single recirculation pump. This results in a reduction factor of 0.75, which is applicable to all fuel types in both Hatch units, being applied to the rated power and flow MAPLHGR limits. For the one-pump seizure accident, two cases of maximum power and maximum core flow for a large-core BWR/4 plant (similar to Plant Hatch) were analyzed, and the MCPR was determined to be greater than the fuel-cladding integrity Safety Limit.

0533C 700775

Georgia Powerkh ENCLOSURE 1 (Continued)

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 dET PUMP SURVEILLANCE i

BASIS FOR CHANGE REQUEST 4

Basis (Continued):

Operation with one recirculation loop results in a maximum power output and core flow which are considerably less than the maximum power and flow attainable during two-loop operation. Therefore, the consequences of abnormal operational transients initiated during SLO will be less severe than those analyzed for a two-l oop operational mode.. NED0-20566 documents that previously analyzed conditions for two-loop operation

bound the fuel thermal-mechanical, boiling transition, and vessel overpressure consequences of one-loop operation for., pressurization and

!, flow increase / decrease transients. However, the Operating Limit MCPR will be 0. 01 higher during SLO, because the Safety Limit MCPR was increased by 0.01 to account for core flow and TIP reading uncertainty.

The rod block monitor (RBM) setpoints are no longer flow-biased since the implementation of the Average Power Range Monitor, Rod Block Monitor, Technical Specifications (ARTS) Improvement Program (Reference 8). The generic rod withdrawal error analysis for ARTS included consideration of SLO. The power-dependent RBM setpoints will not be affected.

i Operation with a single recirculation pump has the potential to increase 4

flow-induced noise in the core instrumentation and increase vibration levels as compared to two-loop operation. This is because at a given core fl ow, SLO will involve higher jet pump flow rates than those -

corresponding to two-pump flow, which tends to cause higher noise levels. These higher noise levels have been evaluated and were found to remain within acceptable vibration limits. The introduction of new LCOs and Surveillance Requirements for jet pump surveillance will require the monitoring of jet pump performance for both single- and two-l oop operation. (See Proposed Change 2, page 5. ) In addition, plant procedures will call for the monitoring of core plate differential pressure noise levels while in SLO and above 45-percent core flow.

The concern regarding the stability of single-loop operation is addressed in that singl e-pump operation in the region where limit cycle oscillations are most likely to occur is not allowed, and the reactor operator is provided with appropriate procedures for detecting and 0533C

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GeorgiaPower m. k ENCLOSURE 1 (Continued)

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 BASIS FOR CHANGE REQUEST Basis (Continued):

suppressing these oscillations. The Technical Specifications Safety and Operating Limits for fuel and the flow-biased APRM STPM scram and rod block setpoints are adjusted conservatively to cover the increased statistical analysis uncertainties associated with operating with a single recirculation pump.

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Georgia Powerkh ENCLOSURE 1 (Continued)

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 BASIS FOR CHANGE REQUEST Proposed Change 2:

This proposed change will _ introduce new LCOs and Surveillance Requirements for jet pump surveillance. These Technical Specifications revisions will be consistent with NUREG/CR-3052 (Reference 2).

Background and Basis:

In conformance with NUREG/CR-3052 recommendations for jet pump beam failure surveillance, the GE-recommended procedure described in the GE SIL No. 330 (Reference 6) was implemented at Plant Hatch. This procedure is identified in the NUREG as one of the accepted methods for detecting jet pump bean failure. As part of the long-term solution to jet pump beam failure, NUREG/CR-3052 proposes that surveillance methods be incorporated into the Technical Specifications instead of being handled through plant procedures.

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Georgia Powerkh ENCLOSURE 1 (Continued)

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-LOOD OPERATION AND dET PUMP SURVEILLANCE BASIS FOR CHANGE REQUEST Proposed Change 3:

This proposed change will update the Bases sections of the Technical Specifications in which the descriptions of transient, accident, and MCPR analyses utilized with the current applicable methodology are presented.

Background and Basis:

As part of this proposed Technical Specifications revision, an update to the Bases sections for transient, accident, and MCPR methodologies is added. The Bases for transient and accident methodologies are revised to reflect the recent analysis described in NEDE-24011-P-A (Reference 4).

The referenced correlation database that describes the MCPR analysis is updated to reflect databases for all fuel types described in NEDE-240ll-P-A. All changes are consistent with the GE Standard Technical Specifications.

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Georgia Powerih ENCLOSURE 1 (Continued)

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 dET PUMP SURVEILLANCE BASIS FOR GHANGE REQUEST

References:

1. General Electric Service Information Letter No. 380, Rev.1, Category 1, dated February 10, 1984 2 "Closcout of IE Bulletin 80-07: BWR Jet Pump Assembly Failure,"

NUREG/CR-3052, published November 1984

3. "Edwin I. Hatch Nuclear Plant Units 1 and 2 Single-Loop Operations,"

NED0-24205, August 1979.

4~. " General Electric Standard Application for Reactor Fuel (Supplement for the United States)," NEDE-240ll-P-A.

5 " General Electric Company Analytical- Model for Loss-of-Cool ant Analysis in Accordance with 10 CFR Appendix K, Amendment No. 2 - One Recirculation Loop Out of Service," NED0-20566-2, July 1978 6 General Electric Service Information Letter No. 330, Errata and Addenda Sheet 80-330-1, December 1980

7. Letter, J. F. Stolz (USNRC) to J. T. Beckham, J r. (GPC), dated September 12, 1985 8 " General Electric BWR Licensing Report: Average Power Range Monitor, Rod Block Monitor and Technical ' Specifications Improvement (ARTS)

Program for Edwin I. Hatch Nuclear Pl ant Units 1 and 2,"

NEDC-30474-P, December 1983 0533C

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GeorgiaPower d ENCLOSURE 2 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:

l SINGLE-LOOP OPERATION AND dET PUMP SURVEILLANCE l 10 CFR 50.92 EVALUATION I

Pursuant to 10 CFR 50.92, Georgia Power Company (GPC) evaluated the proposed Technical Specifications amendment and determined that its adoption would not involve a significant hazards consideration. The bases for this determination are as follows:

Proposed Change 1:

This requested change will revise the MCPR Safety Limit to allow for single-loop operation (SLO). This change requires a 0.01 increase in the Safety Limit, therefore, causing a 0.01 increase in the MCPR Operating Limit as compared to the two-loop Operating Limit.

In addition, a correction factor would be added to the average power range munitor (APRM) md block and simulated thermal power monitor (STPM) scram trip setting actions to preserve the original relationship between core power anc +he actual effective drive flow, when operating with a single loop Also, MAPLHGR curves would be modified conservatively by a derived reduction factor of 0.75 for use during SLO.

The recirculation system Limiting Conditions of Operation (LCOs) and Surveillance Requirements would be changed to allow for SLO. This includes limiting the region in which the plant can operate with a single recirculation pump to core power and flow conditions where limit cycle oscillations are least likely to occur, consistent with GE SIL-380 (Reference 1).

Basis:

The FSAR analyses were reviewed in NED0-24205 (Reference 3), and it was concluded that SLO at reduced power is not more limiting than the abnormal transients and accidents . analyzed for two-loop operation. The l maximum permissible pump speed in SLO was chosen to ensure that vibration i levels would remain within acceptable limits. Stability concerns are '

addressed in the proposed Technical Specifications by limiting the ,

single-loop operating region to outside the region of concern (shown in Figure 2 of Reference 1) and by providing the operator with procedures to detect and suppress limit cycle oscillations. The Safety and Operating i MCPR Limits and the APRM STPM scram and rod block setpoints are conservatively adjusted due to the increased uncertainties in total core flow and traversing- incore probe (TIP) readings. In addition, 'a reduction factor is applied to the MAPLHGR limit to assure that the consequences of the SLO ECCS limiting break are included.

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Georgia Power b ENCLOSURE 2 (Continued)

NRC 00CKETS 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 dET PUMP SURVEILLANCE 10 CFR 50.92 EVALUATION Georgia Power Company has reviewed the proposed revisions and considers them not to involve a significant hazards consideration for the following reasons:

(1) The proposed revisions will not significantly increase the probability or consequences of an accident previously eval uated, because the appropriate setpoints and Operating Limits adjusted for SLO are bounded by the analysis performed for two-loop operation.

(2) The proposed revisions will not create the possibility of a new or different accident from any accident previously evaluated. Although the proposed Technical Specifications revision introduce a new mode of operation, the consequences of SLO have been thoroughly evaluated and are within the bounds of the FSAR analysis.

(3) The proposed revisions will not involve a significant reduction in a margin of safety because the proposed Technical Specifications adjust the approp,iate r setpoints and Operating Limits for SLO to maintain or improve the current margin of safety.

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Georgia Powerkh ENCLOSURE 2 (Continued)

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 dET PUMP SURVEILLANCE 10 CFR 50.92 EVALUATION Proposed Change 2:

This proposed change will revise the jet pump surveillance Techno Specifications to reflect the procedure recommended in GE SIL-3a (Reference 5). These recommendations are currently being implemented through plant procedures.

Basis:

The procedure outlined in Reference 5 is one of the recommended procedures identified in NUREG/CR-3052 (Reference 2). This procedure was selected, because it is more likely than the other procedures to detect a deteriorating jet pump condition prior to a structural failure and it already has been incorporated into the procedures for Plant Hatch. As part of a long-term solution to the concerns identified in IE Bulletin 80-07, NUREG/CR-3052 recommended that this procedure be included in the Technical Specifications.

Georgia Power Company reviewed the proposed changes and considers them not to involve a significant hazards consideration for the following reasons:

(1) The proposed revision will not significantly increase the probability or consequences of an accident previously evaluated, because this ,

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revision reflects the approved plant procedures for detecting and responding to jet pump beam fail ures. This revision does not i introduce any changes to the jet pump performance. )

(2) The proposed revision will not create the possibility of a new or different accident from any accident previously evaluated, because this revision does not involve any physical changes to the jet pumps and does not alter their current modes of operation.

(3) The proposed revision will not involve a significant reduction in a margin of safety, because this revision will reflect only the current procedure for detecting jet pump beam failure in accordance with NUREG/CR-3052 l

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Georgia Powerk s' ENCLOSURE 2 (Continued)

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 10 CFR 50.92 EVALUATION Proposed Change 3:

This change will update the Bases sections in the Technical  !

Specifications in which the descriptions of transient, accident, and MCPR analyses utilized with the current applicable methodology are represented.

Basis:

As part of the above-mentioned proposed Technical Specifications revisions, an update to the Bases sections for transient, accident, and MCPR methodologies is added. The Bases sections for transient and accident methodologies are updated to reflect the current analyses described in NEDE-24011-P-A (Reference 4). The referenced correlation 1

database that describes the MCPR analysis is updated to reflect databases for all fuel types described in NEDE-24011-P-A. All changes are consistent with the GE BWR/4 Standard Technical Specifications.

Georgia Power Company has reviewed this proposed revision and considers it not to involve a significant hazards consideration, because this revision represents a purely administrative change to the Technical Specifications. Consequently, this revision is consistent with Item (i) of the " Examples of Amendments that are Considered Not Likely to Involve a Significant Hazards Consideration," page 14,870 of the April 6,1983, issue of the Federal Register.

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GeorgiaPowerkn

, ENCLOSURE 2 (Continued)

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 DEI PUMP SURVEILLANCE 10 GFR 50.92 EVALUATION

References:

1. General Electric Service Information Letter No. 380, Rev.1, Category 1, dated February 10, 1984

2. " Closeout of IE Bulletin 80-07: BWR Jet Pump Assembly Failure,"

NUREG/CR-3052, published November 1984 3 "Edwin I. Hatch Nuclear Plant Units 1 and 2 Single-loop Operation,"

NED0-24205, August 1979.

4 " General Electric Standard Application for Reactor Fuel (Supplement for United States)," NEDE-240ll-P-A.

5 General Electric Service Information Letter No. 330, Errata and Addenda Sheet 80-330-1, December 1980 I

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