ML20214Q961
| ML20214Q961 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 05/28/1987 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214Q963 | List: |
| References | |
| TAC-64778, NUDOCS 8706050279 | |
| Download: ML20214Q961 (9) | |
Text
4 UNITED STATES O
h NUCLEAR REGULATORY COMMISSION h
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WASHINGTON, D. C. 20655
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GEORGIA POWER COMPANY
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OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE 4
Amendment No. 138 License No. DPR-57 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-57 filed by Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensee) dated February 6,1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR 1
Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not te inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
t 8706050279 870528 PDR ADOCK 05000321 P
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Accordingly, the license is amended by changes to the Technical Specif1-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-57 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications ' contained in Appendices A and B, as revised through Amendment No.138, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
T11s license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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B. J. Youngblood, Director Project Directorate II-3 Division of Reactor Projects-I/II-
Attachment:
Changes to the Technical Specifications Date of Issuance: May 28, 1987
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ATTACHMENT TO LICENSE AMENDMENT NO.138 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. The overleaf pages are provided for convenience.
Remove Insert Page Page 3.4-1 3.4-1 3.4-4 3.4-4 3.4-5 3.4-5 3.4-6 Figure 3.4-1 Figure 3.4-1 Figure 3.4-2 Figure 3.4-2 I
1 i
.1
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.4.
STAN08Y LIQUID CONTROL SYSTEM 4.4 STAN08Y LIOUID CONTROL SYSTEM.
4 Aeolicability Anolicability The Limiting tonditions for Opera-The Surveillance Requirements apply tion apply to the operating status to the periodic test and examination i
of the Standby Liquid Control of the Standby Liquid Control System.
System.
Ob_lective Obiective The objective of the Limiting The objective of the Surveillance Conditions for Operation is to Requirements is to verify the oper-assure the availability of a w ability of the Standby Liquid Control system with the capability to System.
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shut down the reactor and main-tain the shutdown condition without the use of control rods.
Specifications Snecifications A.
Normal System Availability A.
Normal Doerational Tests l
During periods when fuel is The operability of the Standby j
in the reactor and prior to Liquid Control System shall be j
startup from the Cold Shut-verified by the performance of j
down Condition the standby the following tests:
1 liquid control system shall be operable except:
1.
When performing control rod 1.
Nonthly drive maintenance, at which At least once per month each time Specification 3.10.E.
pump loop shall be locally shall be met, started and functionally tested by recirculating de-or mineralized water to the test tank.
2.
When eperating with an inoper-2.
Each Goeratino Cvele able component, at which time At least once during each oper-1 Specification 3.4.B. shall be ating cycle:-
t
- met, a.
Check that the setting of or the system relief valve is 1325 t 75 psig.
3.
When the reactor is in the b.
Verify that each pump will Cold Shutdown Condition and deliver 41.2 gpm against a i
all control rods capable of sy: Me head of at least 1190 normal insertion are inserted psig.
and the requirements of Speci-c.
Initiate one of the Standby t
fication 3.3.A. are met.
Liquid Control System loops I
from the control room after i
arranging suction from the test tank cnd pump dominer-alized water into the reactor HATCH - UNIT 1
- 3. 4-1 Amendment No. 138
_ _ _ --_ _.. - _ _ _ _ _ _. - -.... - - _ -. _ -., _ _. _ _ - - - - - _...., - - _ _ - _ _ _ _ _ _. _ _. _., ~ _. _ - _ - _,. _
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 9
4.4. A.2. Each Operating Cycle (Continued)
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s
- c. vessel. This test checks the
' explosive' charge, proper opera-tion of the ass 5ciated valves -
and selected pump operability.
The replacement charge,to be installed will be selected from a manufactured batch which has been tested.
- d. Both loops including both explo-sive valves should be tested in the course of two operating cycles.
3.4.B._ Operating with Inoperable
_ Components B. _S_urveillance with Inoperable Components If one Standby Liquid Control redundant comp 6nent is inoperable When a component is found to be the reactor may remain in operation inoperable, its redundant com-for a period not to exceed seven ponent shall be demonstrated to (7) days provided the redundant be operable immediately and daily component is operable.
thereafter until the inoperable -
component is repaired. Continuity of the explosive charge is considered a demonstration of operability.
C. _ Sodium Pentaborate Solution C. Sodium Pentaborate Solution At all times when the Standby Liquid Control System is re-The following tests shall be quired to be operable the performed to veri.y the avail-following conditions shall be ability of the liquid control met:
sclution:
- 1. Volume
- 1. Volume The volume of the liquid control solution in the Check the standby liquid liquid control tank shall dontrol tank volume at least be maintained as required once per day, in Figure 3.4-1.
- 2. _ Concentration
- 2. _ Concentration The concentration of the
_ quid control tank shall Check the concentration of the be maintained as required liquid in the standby liquid in Figure 3.4-1.
control tank by chemical analysis:
3.4-2 mmN=
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8ASES FOR LIMITING CONDITIONS FOR OPERATION aND SURVEILLANCE REQUIREMENTS 3.4.
STAN0tY LIQUID CONTROL SYSTEN s
4 The' standby liquid control (SLC) system provides a backup reactivity control capability to the control rod scram system. The original design
' basis for the, standby liquid control system is to provide a soluble boron concentration to the reactor vessel sufficient to bring the reactor to a cold shutdown. In addition to meeting its original design basis. the i
system must also satisfy the requirements of the ATWS Rule 10 CFR 50.62
)
3 paragraph (c) (4), which requires that the system have a control capacity equivalent to that for a system with an injection rate of 86 gpm of 13 weight percent unenriched sodium pentaborate, normalized to a 251 inch diameter reactor vessel.
1 To meet its original design basis, the SLC system was designed with a sodium pentaborate solution tank, redundant pumps, and redundant explosive injection valves. The tank contains a sodium pentaborate solution of i
sufficient volume, concentration and Bao enrichment to bring the.
reactor to a cold shutdown. The solution is injected into the reactor vessel using one of the redundant pumps.
1 The volume limits in Figure 3.4-1 are calculated such that for a given i
concentration of sodium pentaborate, the tank contains a volume of solution
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adequate to bring the reactor to a cold shutdown, with margin. These i
volume limits are based on gross volume and account for the unusable volume of solution in the tank and suction lines.
3
)
To meet 10 CFR 50.62 Paragraph (c) (4), the system must have a reactivity 4
)
control capacity equivalent to that of a system with an 86 gpm injection i
flow rate of 13 weight percent unenriched sodium pentaborate into a 251 inch diameter reactor vessel. The term ' equivalent reactivity control capacity
- refers to the rate at which the boron isotope Ba* is injected into the reactor core. The standby liquid control system meets this j
requirement by using a sodium pentaborate solution enriched with a higher j
concentration of the Ba* isotope. The minimum concentration limit of 6.2 percent sodium pentaborate solution is based on 60 atomic percent Bao enriched boron in sodium pentaborate and a flow rate of 41.2 gpm.
l The method used to show equivalence with 10 CFR 50.62 is set forth in l
NEDE-31096-P (Ref. 1).
Limiting Conditions for Operation are ' established based on the redundancy i
within the system and the reliability of the control rod scram system.
With the standby liquid control system inoperable, reactor operation for short periods of time is justified because of the reliability of the l
control rod scram system. With one redundant component inoperable, reactor j
operation for longer periods of time is justified because the system could l
still fulfill its function.
i Surveillance requirements are established on a frequency that assures a high system reliability. Thorough testing of the system each operating cycle assures that the system can be actuated from the control room and i
will develop the flow rate required. Replacement of the explosive charges in the valves at regular intervals assures that these valves will not fail 1
due te. deterioration of the charges. Functional testing of the pumps is performed once per month to assure pump operability.
)
l HATCH - UNIT 1 3.4 4 Amendment No. 138 1
j BASES FOR LINITING CONDITIONS FOR OPERATION AND S 3.4.
STAN08Y LIOUID CONTROL SYSTEM (Continued)
- 1 1
The sodium pentaborate solution is carefully monitored to assure its reactivity control capability is maintained.
The enriched sodium pentaborate solution is made by mixing granular, enriched sodium pentaborate with water.
Isotopic tests on the granular sodium pentaborate are performed to verify the actual 858 enrichment, prior to mixing with water.
Once the enrichment is established, only the solution concentration, volume and temperature must be monitored to insure that an adequate amount of reactivity control is available.
Determining the solution-concentration once per 31 days verifies that the solution has not been diluted with water.
Checking the volume once each day will guard against noticeable fluid losses or diluticas, and daily temperature checks will prevent sodium pentaborate precipitation.
I 1
1.
" Anticipated Transients without scram, Response to NRC ATWS Rule, 10 CFR 50.62", NEDE-31096-P, December 1985.
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HATCH - UNIT 1 3.4-5 Amendment No. 138 1
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FIGURE 3.41 SODIUM PENTABORATE SOLUTION VOLUME VERSUS CONCENTRATION REQUIREMENTS l
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Amendment No. 138 t