ML20215C133
| ML20215C133 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/10/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20215C132 | List: |
| References | |
| RTR-NUREG-CR-3052 IEB-80-07, IEB-80-7, TAC-61900, TAC-61901, NUDOCS 8706170593 | |
| Download: ML20215C133 (7) | |
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555 f
SAFETY'EVALUATIONBYTHEOFFICEOFNUCLEARREACTORREGULdTION SUPPORTING AMENDMENTS N05.141 AND 77 TO
. FACILITY OPERATING LICENSES DPR-57 AND NPF-5 i
GEORGIA POWER COMPANY OGLETHURPE POWER CORPORATION MUNICIPAL ELEClkl0 AUlHORllY OF GEORGIA
-j CITY OF DALTON, GEORGIA EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-321 AND 50-366 INTRODUCTION By letter dated June.20,1986 '(Reference 1) Georgia Power Company (GPC/ licensee)
C proposed to change the Technical Specifications (TS) for the Edwin I. Hatch
. Nuclear Plant, Units 1 and 2 to pemit operation of the Hatch plants with only one recirculation loop in operation and to reflect the long-term resolution of jet pump _ surveillance in accordance with the Technical Specifications recommen-
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dations of NUREG/CR-3052, "BWR Jet Pump Assembly Failurf as required by IE Bulletin 80-07.. The' licensee's proposed changes include revision to the average power range monitor (APRM) scram and rod block equations, a new MCPR Safety Limit and MAPLHGR limits, and a revised power-flow map required for continuous operation with a_ single recirculation pump to reflect the recommendations of General Electric Service Information Letter (SIL)-380 Revision 1 (Reference 2).
By letter dated July 22,1986'(Reference 3) the licensee provided a copy of General Electric Company Topical Report, NEDO-24205, "Edwin I. Hatch Nuclear Plant, Units 1 and 2 Single-Loop Operation" which it had referenced in its June 20, 1986 submittal. By letter dated January 2,1987, the licensee cor-rected a typographical error in the bases discussion.
Hatch current TS permit single loop operation (SLO) only for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period for Unit I and a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> period for Unit 2, and there are no provisions for potential alteration of safety and operating limits because of SLO conditions, and no provisions for Thermal-Hydraulic Stability (THS) monitoring, if needed, either for SLO or Two Loop Operation (TLO). Staff concerns regarding the THS analyses and monitoring in relation to the proposed SLO have been largely re-solved in the past year, and a nunber of plants have proposed TS changes to permit SLO; these have been reviewed and accepted by the staff.
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T The staff approved resolution of the THS problem is based primarily on the
'h approval of the GE surveillance mode of " detect and suppress" expressed in the So GE SIL-380._(Reference 2).. This mode of operation may be used for both TLO (in lieu of providing approved THS analysis for each reload cycle) and for SLO.
'h It is now required by the staff for SLO without specific regard to THS analyses.
Le The NRC has recently published two generic letters (References 4 and 5) relating L C;<
to THS and SLO. These generic letters present staff positions in this area, including the criteria for acceptance of surveillance modes reconrnended in A{
SIL-380 and provide a basis for review of TS changes.
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.... EVALUATION There are two principal areas related to SLO which require TS changes. They are (1) changes to some safety and operating limits and instrument setpoints resulting from altered reactor conditions and reanalysis of relevant transient and accident events, and (2) operating limits related to the power-flow map location and monitoring of THS to detect and suppress potential oscillations.
j The Hatch original submittal (Reference 1) presented TS changes and supporting infomation in both areas. The supporting information for changes to limits and setpoints included the report by GE (Reference 3) of the analyses of relevant transients and accidents for SLO for Hatch and the deviation of appropriate limits and operating conditions. The changes to provide monitoring
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and suppression of oscillations were based on SIL-380 and generally patterned after the Duane Arnold TS.
1 The GE analyses of SLO (Reference 3) provide the following changes to Safety Limit (SL) and Operating Limit (0L) Minimum Critical Power Ratio (MCPR) and Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) limits, and to Average Power Range Monitor (APRM) and Rod Block Monitor (RBM) setpoints.
These analyses and changes are similar in content and magnitude to those approved in previous reviews.
(1) SL MCPR and OL MCPR: The SL MCPR is increased by 0.01 to account for
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increased uncertainties in core flow and power distribution measurements.
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The OL MCPR is increased for Hatch by the same amount. Limiting transients were reexamined to assure that this is a sufficient increase throughout the achievable power-flow range. No additional increase in OL MCPR is necessary since transient events initiated from TLO remain limiting. These changes are acceptable.
(2) APRM scram and rod block limit functions: These equations have an added tem to account for the difference between single and two loop drive flow for the same core flow. This adjustment accounts for the difference between actual 1
and indicated flow and preserves the original relation between limits and effective drive flow. These changes are acceptable.
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(3) MAPLHGR: GE has performed a series of LOCA analyses for Hatch to provide ir ;
a MAPLHGR multiplier for this event. The principal change in the. analysis is
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the assumption of an earlier occurring boiling transition. The multiplier for s
Hatch for all GE fuel was determined to be 0.75 (Reference 8). This is acceptable.
j 0ther relevant transients and accidents were examined and evaluated and found l
to require no additional changes to the TS. These included recirculation pump l
seizure, control rod drop, main steamline break, refueling, and fuel assembly o<
loading accidents. The analysis of the SLO recirculation pump seizure accident I
showed that the minimum MCPR for the large core BWR/4 plant remained greater thaw the SLMCPR and that the results of the two-loop analysis for the other four events are conservatively applicable for one-pump operation. These analyses are acceptable.
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. To avoid potential problems of THS in SLO, Hatch has provided new.TS which require that the core flow be maintained greater than or equal to i457 of rated cort flow when core power is greater than or equal to the 80% rod line. These requirements are consistent with the recommendations of SIL-380. This action for TH5 is acceptable.
Some general questions have arisen regarding the adequacy of surveillance methods which have been used in some plants to monitor jet pump operability during SLO. These methods are used in accordance with NUREG/CR-3052 to resolve problems presented in IE Bulletin 80-07, "BWR Jet Pump Assembly Failure." The GE reconinended procedure described in the GE SIL No. 330 (Reference 6) was implemented at plant Hatch. As recuired by IE Bulletin 80-07, this procedure is identified in the NUREG/CR-3052 as one of the accepted methods for detecting jet pump hold down beam failure. This pro-posed incorporation of jet pump surveillance methods into the Technical Specifications is acceptable.
The Hatch Units 1 and 2 Technical Specification Bases section were updated to include infonnation describing abnormal transient and accident analyses and MCPR methodologies (Reference 7). These updated Sections are consistent with currently approved methods and the GE BWR/4 standard Technical Specifi-cations and are acceptable.
To accomplish these changes for SLO limits, THS monitoring, jet pump surveil-lance, the Bases and reference update, the licensee has proposed the following revisions to the TS:
Hatch Unit 1 (1) Specifications 1.1. A, and Bases 1.1. A, 2.1. A.3, 3.2.G.3, 3.6.J and 3.11.B and C: The SLMCPR has been increased by.01 to 1.08 for SLO because of the increased uncertainties in the total core flow and traversing incore probe (TIP) readings.
(2) Specifications 3.6.I and 4.6.I and J, and Basis 3.6.1: The LC0 and operability surveillance for jet pumps are incorporated in accordance
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with NUREG/CR-3052 to resolve problems as required by IE Bulletin 80-07, "BWR Jet Pump Assembly Failure."
j (3) Bases 1.1. A and E, and 2.1 and 2.1.C: The methods and references from 4
NEDE-10958-P-A, NEDE-24011-F-A, and NEDO-24205, " Hatch I and ? single-loop operation" are incorporated into the TS.
(4) Specifications 1.1.A and 2.1.A.I.C(1), Bases 2.1.A.I.C and 3.6.J and Tables 3.1-1 and 3.2-7:
Flow referenced simulated thermal power monitor trip setting (run mode) APRM Flux Scram trip setting (run mode) have an edded delta W term to account for the difference between TLO and SLO drive flow at the same core flow.
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. f (5) Specification 3.11. A. Bases 3.6.J. 3.11. A and 3.11.C and Figure 3.11.1 (Sheet 6): These changes provide for decrease in the MAPLHGRilimit by l
l thennal power, and als$)for an increase in OLMCPR by 0.01 for adding the factor.75 (MAPFAC for SLO when power is greater than 52% of rated words "for two loop operation" and also for making an administrative correction to change reference 10 to reference 7.
i (6) Basis 3.6.J and Figure 3.6.5: These changes provide and describe the i
permissible SLO regions in the power-flow map. The operator is provided
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with appropriate procedures to place the unit in the operation allowed J
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region. This provides a satisfactory representation of the reconnendation l
of SIL-380 and the staff generic position.
j Hatch Unit 2 l
(1) Specifications 2.1.2 and 2.1.3 and Bases 2.1, 3/4.4.1.1 and 3/4.2.3: The j
SLMCPR has been increased by.01 to 1.08 for SLO because of the increased
'l uncertainties in the total core flow and traversing incore probe readings.
A correction of a typographical error to change the word "with" to "within" l
was also made.
(2) Tables 2.2.1-1 and 3.3.5-2 and Basis 2.2.1.2: APRM flow referenced simu-l lated thermal power monitor trip setting has an added delta W term to account for the difference between TLC and SLO drive flow at the same core flow.
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(3) Bases 2.1.2, 2.3 and 3/4.4.9: The approved methods and references are incorporated.
l (4) Specification 3.4.1.1 and Figure 3.4.1.1-1:
This change provides and describes the permissible SLO regions in the power-flow map. The operator I
is provided with appropriate procedures to place the unit in the operation allowed region. This provides a satisfactory representation of the recommendations of SIL-380 and the staff generic position.
(5) Specification 3.4.1.2 and Basis 3/4.4.1.2: As required by IE Bulletin 80-07, one of the acceptable procedures for jet pump fail surveillance identified in NUREG/CR-3052 is incorporated into the Technical l
Specifications, j
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(6) Specification 3.10.4: This is an administrative change for the performance j
of the startup test program and physics tests.
j (7) Bases 3/4.2.1 and 3/4.4.1.1: These changes provide for the decrease in the MAPLHGR limit by the factor 0.75 to account for the assumption of an earlier j
occurring boiling transition (Reference 8).
l (8) Specification 3/4.2.1: The words " applicable limits" are used in LC0 3.2.1 l
and Surveillance 4.2.1.
(9) Figure 3.1.1-11 and Basis 3/4.4.1.1:
This change provides for decrease in the MAPLHGR limit by the factor.75 (MAPFAC ) for SLO when power is greater p
than 52% of rated thermal power.
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, L (10)-Basis 3/4.2: The references are updated.
4 (11) Basis 3/4.4.1~.1: This change'is for-the thermal-hydraulic stability for SLO in accordance with SIL-380, Revision 1 to' preclude the possibility of experiencing limit cycle oscillations during SLO.
-(12) Specification 4.4.1.1.2:
This is a new specification that provides additional surveillance for. SLO and is used to verify _that the reactor.
is ~ operating in the allowed region.
'(13) Specification 4.4.1.2: This change modifies the surveillance requirements for jet pump operation and is in accordance with IE Bulletin 80-07 requirements.
. e have reviewed GPC's' June 20, 1986 request proposing TS changes relating to W
SLO,. including _ jet pump surveillance and the other documents submitted by GPC-in support of this request. Based on this review we conclude that appropriate documentation was submitted and that the' proposed changes' assure conformance
-with the General' Design Criteria 10 and 12, and 10 CFR 50 Appendix A, and with staff requirements,in this area, and are therefore acceptable.
.ENVIRONFENTAL CONSIDERATIONS The ' amendments change 'a' requirement with respect _ to installation or use of a l
facility component located within the. restricted area as _ defined in 10 CFR Part 20. The staff has determined that the amendments involve no significar.t increase in the amounts, and no significant change in the types, of_ any ef-fluents that may.be released offsite, and that there should be no significant' l
increase in individual-or cumulative occupational radiation exposure. The Comission has previously issued a proposed finding that the amendments in-volve no significant hazards consideration and there has been no public i
coment on such finding. Accordingly, the amendments meet the eligibility.
j criteria' for categorical exclusion set forth in 10 CFR 651.22(c)(9). Pursuant to'10 CFR 551.22(b), no environmental impact statement or environmental assess-1 ment need be prepared in connection with the issuance of the amendments.
1 CONCLUSION
.The Comission made a proposed determination that the amendments involve no significant hazards consideration which was published in the Federal Reoister (51 FR 30572) on August 27, 1986, and consulted with the state of Georgia. No public comments were received, and the state of Georgia'did not have any l
coments.
We have concluded, based on the considerations discussed above, that: -(1) there is reasonable assurance that the health and safety of the public will not be en-dangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Comission's regulations, and the issuance'of the' amendments will not be inimical to the comon defense and security or to the health and safety of the public, s
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.. REFERENCES 1.
Letter, J. T. Beckham, Jr. (GPC) to Director of ONRR, (NRC).
kequest to Revise Technical Specifications: Single-Loop Operation and Jet Pump Surveillance June 20, 1986.
2.
General Electric Service Information, Letter No. 380, Rev.1 Category 1, February 10, 1984 3.
Letter, L. T. Gucwa (GPC) to Director of ONRR (NRC), Request to Revise Technical Specifications: Single-Loop Operation and Jet Pump Surveillance, dated July 22, 1986, enclosing a GE Report, NED0-24205, Edwin I. Hatch Nuclear-Plant Units 1 and 2 Single-Loop Operation, August 1979.
4.
Generic Letter No. 86-02, " Technical Resolution of Generic Issue No.
B-19-Thermal-Hydraulic Stability," January 23, 1986.
5.
Generic Letter No. 86-09, " Technical Resolution of Generic Issue No.
B-59-(N-1) Loop Operation in BWRs and PWRs," March 31, 1986.
6.
General Electric Service Infonration Letter No. 330, through the December 1, 1980 update.
7.
" General Electric Standard Application for Reactor Fuel Supplement for the United States," NEDE-24011-P-A-7, August 1985.
8.
" General Electric Company Analytical Model for loss-of-Coolant Analysis in Accordance with 10 CFR 50 Appendix K, Amendment No. 2 - One Recirculation Loop Out of Service," NE00-20566-2, July 1978.
Principal Contributors:
T. Huang L. Crocker Dated: June 10, 1987 l
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1 DATED June'10, 1987 g-AMENDMENT NO.141T0 FACILITY OPERATING LICENSE DPR-57, EDWIN I. HATCH, UNITS 1 & 2
-j AMENDMENT NO. 77TO FACILITY OPERATING LICENSE NPF-05, EDWIN I. HATCH, UNITS 1 & 2 j
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Docket F11e 3 hhv PUK Local PDR PRC System PD#II-3 Reading M. Duncan L. Crocker B. J. Youngblood D. Hagan T.Barnhart(8)
E.-Butcher W. Jones ACRS(10)
OGC-Bethesda GPA/PA ARM /LSMB S. Varga G. Lainas J. Partlow E. Jordan T. Huang L. Reyes 9
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