ML20247E598
| ML20247E598 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/18/1989 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247E602 | List: |
| References | |
| NUDOCS 8907260228 | |
| Download: ML20247E598 (13) | |
Text
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GEORGIA POWER COMPANY 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 Amendment No.
165 License No. DPR-57 1
~1.
The Nuclear Regulatory Comission (the Comission) has found that:
The app (lication for amendment to the Edwin 1. hatch Nuclear Plant, A.
Unit 1 the facility) Facility Operating License No. DPR-57 filed by Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municiaal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensee) dated September 6,1988, complies.with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR 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 (i) 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 Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and 4
E.
The issuance. of this amendment is in accordance with 10 CFR Part 51 i
of the Comission's regulations and all applicable requirements have 1
been satisfied.
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Accordingly, the-license is amended by changes to the Technical Specifi-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 Aandment No.'165, nre hereby incorporated in the
. license. The licensee shall operate the. facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/s/
David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 18, 1989 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 165 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 amenament number and contain vertical lines indicating the area of change.
Remove Page Jnsert Page 3.7-1 3.7-1 3.7-la 3.7-la 3.7-30 3.7-30 i
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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT 5 3.7.
CONTAINMENT SYSTENS 4.7.
CONTAINMENT SYSTEMS j
q Ano11 cab 111tv Ano11c' ability The Limiting Conditions for Operation The $ surveillance Requirements associated with containment systems:
associated with containment systems.
l apply to the operating status of the primary and secondary containment
. apply to the primary and secondary
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containment integrity.
systems.
Objective Obiective The objective of the Limiting' Conditions The objective of the Surveillance Re' for Operation is to assure the integrity quirements is to verify the integrity of the primary and secondary containment. of the primary and secondary contain--
systems.
ment.
Specifications specifications A.
Pressure Sucoression Chamber 1.
Pressure sucoression Chamber-At any time that irradiated a.
The pressure suppression chamber, fuel is in the reactor vessel, and water level, water temperature the nuclear system is pressurized and air temperature shall be above atmospheric pressure or measured and recorded daily.
work is being done which has the potential to drain the vessel, the pressure suppression chamber
- b..The interior painted surfaces water level and wat*er temperature above the level 1. foot below shall be maintained within the the nonnel water line of the following limits except while per-pressure suppression chamber forming low-power physics tests at shall'be visually inspected atmospheric pressure at power levels once per operating cycle, not to exceed 5 ht.
In addition, the external surfaces of the pressure a.
Minimum water level - 12 feet, suppression chamber shall 2 inches.
be visually inspected on a routine basis for evidence b.
Maximum water level - 12 feet, of corrosion or leakage, 6 inches.
c.
Whenever there 15 indicatio'n c.
During normal power operation, that a significant amount of the suppression chamber water heat is being added to the temperature shall be maintained l-pressure suppression pool, the
$ 100*F. If this temperature pool temperature shall be con-limit is exceeded, pool cooling tinually nonitored and also shall be initiated insediately, observed and logged every 5 I
minutes until the heat addition if the water temperature cannot l is terminated, be restored to 5100*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor shall be shut down using normal shutdown procedures.
1 HATCH - UNIT 1 3.7-1 Anendnent No. 165 l
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LIMtitNG CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS d.
During relief valve operation or d.
Whenever there is testing of RCIC, HPCI, or other indication that there j
testing which adds heat to the was relief valve operation i
suppression pool, the maximum with the temperature of j
water temperature shall not the suppression pool exceed 105'F.
In connection exceeding 160'F and the with such testing, the pool reactor primary coolant temperature must be reduced l
system pressure greater.
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to 1. 100*F.
l than 200 psig, an ex-ternal visual examination e.
The reactor shall be scrammed of the pressure suppres-l from any operating condition sion chamber shall be i
when the suppression pool conducted before resuming temperature reaches 110'F.
power operation.
Operation shall not be re-sumed until the pool l
temperature is reduced to below the normal power operation limit specified in c. above, r
f.
During reactor isolation conditions the reactor pressure vessel shall be depressurized to < 200 psig at normal cooldown rates if the pool temperature reaches 120'F.
HATCH - UNIT 1 3.l.14 Anen ' ent No.165 i
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BASES FOR LIMITING CONDITIONS FOR OPERATION
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= 3. 7. A.'1. : Pressure Suneression Chamber (' ontinued)
C The maximum pool temperature based on the consideration of complete condensa-tion has been detennined by evaluating the blowdown test data f rom the' Mark I Full Scale Test Facility. Based on these analyses, a pool temperature of 195'F can provide complete steam condensation (conservatively assumes no pressurization of the air space over the pool). Analyses for Plant Hatch have shown that with an initial pool temperature of 110*F. the pool temperature following a blowdown will be below that needed for complete -
condensation. Therefore the 100'F limit on operating pool temperature is justified.
For sn initial suppression pool temperature of 110'F and assuming that one loop of the RHR system is available for Containment cooling (2 RNR and 2 RHR service water pumps) adequate not positive suction head (NPSH) is maintained for the core spray, RHR and HPCI pumps. Therefore, the 100*F limit on oper.-
.ating pool. temperature is justified.
Limiting pressure suppression chamber water, temperature to 120*F during RCIC, j
HPCI or relief valve operation when decay heat and stored energy are removed '
from the primary system by discharging reactor steam directly to ths sup-pression chamber assures adequate margin for controlled blowdown anytime-during RCIC operation, i
Using a 50'F rise (Table 5.2-1 FSAR) in the pressure suppression chamber-water temperature and an initial temperature of < 120'F. the 195+F limit h
is not exceeded.
If a loss-of-coolant accident were to occur when the reactor water temperature is below 330'F. containment pressure will not exceed the 62 psig maximum pressure even if no condensation were to occur. The maximum allowable pressure suppression chamber water temperature..whenever the reactor is above 212*F. shall be governed by this specification. Thus specifying combinations of water volume and temperature requirements applicable for a
reactor-water temperatures above 212'F provides additional margin above' that available.at 330'F.
Should it be necessary to drain the pressure suppression chamber, this should -
only be done when there is no requirement for core standby cooling systems operability, as explained in basis 3.5.6.
2.
Primary Containment Inteerity Discussed under Bases for Specification 3.7.A., Primary Containment.
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1 3.
Reactor Guildina to Pressure Sunnression Chamber Vacuum Relief Svstem The purpose of the reactor building to pressure suppression chamber vacuum relief system is to equalize pressure so that the structural integrity of the containment is assured.
The vacuum relief system from the reactor building to the pressure suppression l
chamber consists of two 100-percent vacuum relief lines, each of which has an
~ air operated valve and a vacuum breaker (check valve) in series. Operation of either line will maintain the pressure differential less than 2 psid, the external design pressure. Reference Section 5.2.3.6.2 of the FSAR.
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HATCH - UNIT 1 3.7-30 Amendnent ba. 165 i
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GEORGIA POWER COMPANY
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OGLETHORPE POWEP CORPORATION FUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DAL10N, GEORGIA DOCKET NO. 50-366-EDWIN 1. HATCH NUCLEAR PLANT, UNIT NO. 2
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AMENDHENT TO FACILITY OPERATING LICENSE 1
1 Amendment No. 102 License No. NPF-5 t
1.
The Nuclear Regulatory Comission (the Commission) has found that:
l The app (licatiun for amendment to the Edwin I. Hatch Nuclear Plant, A.
Unit 2 the facility) Facility Operating License No. NPF-5 filed q
by Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licer.see) dated Septenber 6,1988, complies with the' standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR 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 (i) that the activities authorized by this enendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in cospliance with the Comission's regulations set forth in 10 CFR Chapter I; i
i D.
The issuance of this amendment will not be 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 CFP Part 51 l
of the Comission's regulations and all applicable requirements have j
been satisfied.
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Accordingly, the license is anended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.0.(2) of Facility Operating License No. NPF-5 is hereby amended to read as follows:
(2)~ Technical Specifications The Technical Specifications contained in' Appendices A and B, as revised through Amendment No.102, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.s This itcense ' amendment is effective as of its' date of issuance and shall be implemented within 60 days of-issuance.
FOR THE NUCLEAR REGULATORY COMMISSION' (SJ
+-
David B. Matthews,-Director Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation H
Attachment:
Changes to the Technical Specifications
'Date of Issuance: July 18, 1989 OFFICIAL RECORD C0P O
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ATTACHMENT TO LICENSE AMENDMENT NO.102 FACILITY CPERATING LICENSE NO. NPF-5 l-DOCKET N0. 50-366 l-Replace the following pages of the Appenaix A Technical Specifications with l
the enclosed pages. The revised pages are identified by amendment number and l
contain vertical lines indicating the area of change.
Remove Page Insert Page 3/4 6-11 3/4 6-11 3/4 6-12 3/4 6-12 3/4 6-13 3/4 6-13 B3/4 6-3 B3/4 6-3 l
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' CONTAINMENT SYSTEMS 3/4 6.2 DEPRESSURIZATION SYSTEMS SUPPRESSION CHAMBER LIMITING CONDITION FOR OPERATION l
3.6.2.1 The suppression chamber shall be OPERABLE with the pool water:
Volume between 87,300 ft', and 90,550 ft', equivalent to a a.
level between 12 ft 2 in, and 12 ft 6 in., and a l'
b.
Maximum temperature of 100'F during OPERATIONAL CONDITION 1 or l
l 2, except that the maximum temperature may be permitted to increase to:
1.
105'F during testing which adds heat to the suppression chamber during OPERATIONAL CONDITION 1 or 2, 2.
120*F with the main steam line isolation valves closed.
following a scram from OPERATIONAL CONDITION 1 or 2.
c.
Level instrumentation channels alarms adjusted to actuate at:
1.
High water level of s 12.ft 6 in.
2.
Low water level of 2 12 ft 2 in.
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l APPLICABILITY: CONDITIONS 1, 2 and 3.
ACTION:
j a.
With the suppression chamber water volume outside the above limits, restore the volume to within the limits within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUT 00WN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
In OPERATIONAL CONDITION 1 or 2 with the suppression chamber water temperature > 100*F, except as permitted above, initiate suppression pool cooling and restore the temperature to s 100*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUT 00WN w'ithin the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
1 c.
In OPERATIONAL CONDITION 1 or 2 with the suppression chamber water temperature > 105'F during testing which adds heat to the suppression chamber, stop all testing, initiate suppres-sion pool cooling and restore the temperature to 5 100*F within l
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUT 00WN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
HATCH - UNIT 2 3/4 6-11 Anendment flo. 102
CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)
ACTION: (Continued) d.
In OPERATIONAL CONDITION 1 or 2 with THERMAL' POWER > 1 percent of RATED THERMAL POWER and the suppression chamber water temperature
> 110*F, place the reactor mode switch in the Shutdown position, e.
With the suppression chamber water temperature > 120'F and the main steam isolation valves closed following a scram from OPERATIONAL CONDITION 1 or 2, depressurize the reactor pressure vessel to < 200 psig at normal cooldown rates, f.
With one suppression chamber water level instrumentation channel inoperable, restore the inoperable channel to OPERABLE status within 30 days or ce in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
g.
With both suppression chamber water level instrumentation channels inoperable, restore at least one inoperable channel to OPERABLE status within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the follow-ing 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.2.1 The suppression chamber shall be demonstrated OPERABLE:
a.
By verifying the suppression chamber water volume to be between 12 ft 2 in. and 12 ft 6 in. at least once per 24 hoars b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in OPERATIONAL CONDITION 1 or 2 by verifying the suppression chamber water temperature to be 5 100*F.
l c.
At least once per 5 minutes in OPERATIONAL CONDITION 1 or 2 during testing which adds heat to the suppression chamber, by l
verifying the suppression chamber water temperature s 105'F.
d.
At least once per 60 minutes when THERMAL POWER > 1 percent
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of RATED THERMAL POWER and suppression chamber water temperature l
> 100'F, by verifying suppression chamber water temperature l
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< 110*F.
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HATCH - UNIT 2 3/4 6-12 Mendment No. 102 1
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r CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) i At least once per 30 minutes following a scram from OPERATIONAL e.
CONDITION 1 or 2 with the main steam line isolation valves closed, and suppression chamber water temperature > 100'F, by l
verifying suppression chamber water temperature < 120*F.
f.
By~an external visual examination of the suppression chamber.-
after there has been indication of safety / relief valve opera-tion with the suppression chamber water temperature 2 160'F and reactor coolant system pressure > 200 psig.
l-g.
At least once per 18 months by a visual inspection of the accessible interior and exterior of the suppression chamber.
h.
.By verifying two suppression chamber water level instruments-tion channels (2T48-R607A,B) OPERABLE by performance of a:
1.
CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 2.
CHANNEL FUNCTIONAL TEST at least once per 31 days, and 3.
CHANNEL CALIBRATION at' least once per 6 months.
HATCH - UNIT 2 3/4 6-13 Amendnent No. 102 I
CONTAINMENT SYSTEMS BASES 3/4.6.2 DEPRESSURIZATION SYSTEMS The specifications of this section ensure that the primary containment pressure will not exceed the maximum allowable internal pressure of 62 psig during primary system blowdown from full operating pressure.
The suppression chamber water provides the heat sink for the reactor coolant system energy release following a postulated rupture of the system.
The suppression chamber water volume must absorb the associated decay and structural sensible heat released during reactor coolant system blowdown from 1040 psig. Since all of the gases in the drywell are purged into the suppression chamber air space during a LOCA, the pressure of the liquid must not exceed 62 psig, the suppression chamber maximum pressure. The design volume of the suppression chamber, water and air, was obtained by considering that the total volume of reactor coolant to be condensed is discharged to the suppression chamber and that the drywell volume is purged to the suppression chamber.
Using the minimum or maximum water levels given in the specification, containment pressure during the design basis accident is approximately 57.5 psig which is below the maximum allowable internal pressure of 62 psig.
Maximum water level results in a downcomer submergence of 4 ft 4 in, and the minimum water level results in a submergence approximately 4 in. less. The Mark I Full Scale Test Facility tests were performed at several submergence levels which bound this variance, all with complete condensation. Thus, with respect to the downcomer submergence, this specification is adequate.
The maximum pool temperature based on the consideration of complete condensation has been determined by evaluating the blowdown test data from the Mark I Full Scale Test Facility. Based on these analyses, a pool temperature of 195'F can provide complete steam condensation (conser-vatively assumes no pressurization of the air space over the pool).
Analyses for Plant Hatch have shown that with an initial pool temperature of 110*F, the pool temperature following a blowdown will be below that needed for complete condensation. Therefore, the 100'F limit on operating pool temperature is justified.
For an initial suppression pool temperature of 110'F and assuming that one loop of the RHR system is available for containment cooling (2 RHR and 2 RHR service water pumps), adequate net positive suction head (NPSH) is maintained for the core spray, RHR, and HpCI pumps. Therefore, the 100'F limit on operating pool temperature is justified.
When it is necessary to make the suppression chamber inoperable, this shall only be done as provided in Specification 3.5.4.
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HATCH - UNIT 2 B 3/4 6-3 Amendment No. 102
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