ML20141A518
| ML20141A518 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/26/1986 |
| From: | Miller D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20141A522 | List: |
| References | |
| TAC-53454, TAC-53455, NUDOCS 8604040498 | |
| Download: ML20141A518 (12) | |
Text
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8 UNITED STATES
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NUCLEAR REGULATORY COMMISSION h
WASHINGTON, D. C. 20555
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GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA i
CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN 1. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.124 License No. DPR-57 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Georgia Power Company, et.al.,
(the licensee) dated December 21, 1983 as modified by letter dated April 16, 1984, 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 Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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; 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 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications 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:
B604040498 860326 PDR ADOCK 05000321 P
PDR j
. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.124, are hereby incorpcrated 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 4
shall be implerented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION
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Daniel R. Muller, Director Bk'R Project Directorate #2 Division of BWR Licensing 1
Attachment:
Changes to the Technical Specifications Date of Issuar.ce: March 26, 1986 l
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ATTACHMENT TO LICENSE AMENDMENT N0.124 i
_ FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 l
Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 3.1-22 3.2-22 3.2-23a 3.2-23a 3.2-48 3.2-48 3.7-33 3.7-33 3.7-39 3.7-39 i
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r Table 3.2-11 INSTRUMENTATION WHICH PROVIDES S'JRVEILLANCE INFORMATION g
a Required
- s Operable
" Ref.
y No.
Instrument Instrument Type and Channels Range Action Remarks (a)
(b)
UU 1
Recorder -150" to +60a (c)
(d) 1 Reactor Vessel Water Level Indicator -150" to,+60" (c)
(d) 2
. 2 1
Recorder -317" to -17" (c)
(d) 2 Shroud Water Level 3
1 Indicator -317" to -17" (c)
(d) 1 Recorder 0 to 1500 psig (c)
(d) 3 Reactor Pressure 2
Indicator 0 to 1500 psig (c)
(d)
E 2
Recorder -10 to +90 psig (c)
(d) 4 Dryw11 Pressure 2
Recorder 0 to 500*F (c)
(d) 2 5 Drywell Temperature 2
Recorder 0 to ';00*F (c)
(d) 6 Suppression Ciaanber Air Temperature 2
Recorder 0 to 250*F (c)
(d) h7 Suppression Chamber Water Temperature 2
Indicator 0 to 300" (c)
(d) 1 8
Suppression Chamber Water Level 2
Recorder 0 to 30" (c)(e)
(d) 2 Recorder -10 to +90 psig (c)
(d) 9 Suppression Chamber Pressure Rod Position Information System (RPIS) 1 28 Volt Indicating Lights (c)
(d) 10 1
Recorder 0 to 5%
(1)
(d),l 4
11 Hydrogen and Oxygen Analyzer 12 Post LOCA Radiation Hon,toring System 1
Recorder (c)
(d) 8 R/hr (c)
(d)
Ind'icator 1 to 10 13 a)' Safety / Relief Valve Position Primary 1/SRV Indicating Light at 85 psig (f)
Indicator b) Safety / Relief Valve Position Secondary 1
Recorder 0 to 600 F tf)
Indicator
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s N0fES RR TABLE 3.2-11 (Cont.imed)
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With the plant in the power operation, startty, or hot shutdown comittion and with the mober of g.
d operable channels less than the required operable channels, initiate the. preplanned alternate j
g method of monitoring the appropriate parameter within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> aml:
either restore the inoperabl,e channel (s) to operable status within 7 days of the event, or d
1.
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prepare and subett a special report to the NRC pursuant to Specification 6.9.2 within 14 days A
followire the event outlinin2 the action taken, the cause of the t'noperability, ami the plans and schedule for restoring the system to operable status.
h.
A channel contains two detectors:
one for mid-range noble gas, amt one for high range noble gas.
Both detectors must be operable to consider the channel operable.
1.
Instrumentation shall be operable with continuous sampling capability within 30 minutes of an ECCS actuation during a LOCA. See Section 3.7.A.6.c for the LIMITING CONDITION FOR OPERATION.
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Q Table 4.2-11 Check and Calibration Minimum frequency for Instrumentation 7'
Which Provides Surveillance Information f.
o S
Ref.
Instrument Instrument Check Instrucent Calibration 5
No.
Minimum frequency Minimum Frequency (b)
(c) g (a)
C 1
Reactor Vessel Water Level Each shift Once/ operating cycle (f)
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Each shift Once/ operating cycle (f) 2 Shroud Water Level 3
Reactor Pressure Each shift Once/ operating cycle (f)
Lach shift Every 6 months 4
Drywell Pressure 5
Drywell Temperature Each shift Every 6 months 6
Suppression Chamber Air Each shift Every 6 months Temperature 7
Suppression Chamber Water Each shift Every 6 months Temperature 8
Suppression Chamber Water Each shift Every 6 months
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level m
9 Suppression Chamber Each shift Every 6 months Pressure 10 Rod Position Information Each shift N/A System (RPIS) 11 Hydrogen and Oxygen Monthly Every 3 months Analyzer 12 Post LOCA Radiation Each shift Every 6 months 13 a) Safety / Relief Valve Position Pri-Monthly Every 18 months mary Indicator b) Safety / Relief Valv. Position Monthly Every 18 months Secondary Indicato,r
BASES FOR LIMITING COPOITIONS FOR OPERATION
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3.7.A.5 0xygen Concentration (Continued)
The occurrence of primary system leakage following a major refueling outage or other scheduled shutdown is much more probable than the occurrence of the loss-of-coalant accident <Jpan which the specified oxygen concentration limit is based.
Permitting access to the drywell for leak inspections during e startup is judged l
prudent in terms of the added plant safety offered without significantly reducing the margin of. safety. Thus, to preclude the possibility of starting the reactor and opeating for extended periods of time with significant leaks in the primary systen, leak inspections are scheduled during startup periods, when the primary systen is at or near rated operating temperature and pressure. The 24-hour period to provide inerting is judged to be sufficient to perform the leak inspection and establish the required oxygen concentration.
The primary contairunent is norma 1Jy slightly pressurized during periods of reactor operation.
Nitrogen used for inerting could leak out of the containment but air could not leak in tc 2 crease oxygen concentration.
- 6. Containment Atmosphere Dilution (CAD)
In order to ensure that the containment atm0 sphere remains inerted, i.e., the oxygeri-hydrogen mixture is maintained below the flanmable limit, the capability to inject nitrogen into the containment after a LOCA is provided.
The post-LOCA Containment Atmosphere Dilution systen design basis and description are presented in Section j
5.2.4.9 of the FSAR.
By maintaining at least a 7-issy supply of nitrogen onsite, there will be sufficient time after the occurrence of a LOCA for obtaining additional nitrogen from Icczl c:mnercial sources.
The H2 and 02 analyzer systen is a redundant system consisting of two H2 analyzers and twe 02 analyzers with a sampling system which provides for four sampling points.
Two sample lines are connected to the drywell and two are conrncted to the torus.
One Hg analyzer and one 02 analyzer samole the drywell while the otner H2 and 02 analyzers sample the torus.
Using a system of automatic valves, the sample lines are switched to provide sampling fra different areas of the drywell and the torus.
This system provides periodic but continuous post.LOCA sampling alternately l
fran the two drywall sample points' esd the two torus sample points. Thu period of sampling from each point is adjustable.
l Due to i.he nitrogen addition, the pressure in the containment after r LOCA will increase with time.
Under the worst expected c onditions, the cantainment pressure will reach 30 peig in approximately 20 days.
If and when that pressure is reached, venting from the primary r.untairinent shall be manually initjttad..
The verting path will inciule the stan@y gas treatment system and the main stack in order to minimize the offsite dose.
3.7-33 Amendment No.
124
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SASES FOR SLRVEILLANCE REQUIREENTS i
4.7.A.6. Containment Atmosphere Dilution (CAD)
I As discussed in the Bases fdr Specification 3.7.A.6, the H2 02 analyzer system is radundant and flexible by design.
If either an H2 or 0
analyzer
- fails, the periodic sampling remains unchanged, 2since the second H2 and 02 analyzer is still in service.
For nomal operation, a monthly calibration check using l
known samples will be adequate to detemine the operability and calibration of each analyzer and to ensure the system's reliability.
B.
Standby Gas Treatment System and C.
5s:ancary Containmen_t, PrcJsure drop across tMe combined EPA filters and charcoal adsorbers of less than 6 inches of water t4t the system design flow rate will indicate that the filters and adsorbers are nQt clogged by exedssive amounts of foreign matter.
A test frequency of once l
per operating cycle estchlished systQc perfemance capability.
The frequency of tests and sample analysis are necessary to show that the EPA filters and charcoal adsorbers can perfom as evaluated.
Repiccament adf.orhant should be qualified according to the guidelines of Regulatory Guide 1.52.
The charcoal adsorber efficinney test procMures should allow for the removal of one adsorber tray, mptying of one bed fron the tray, mixing the adsostant thoroughly and obtaining at least two samples.
Each sample should be at least two inches in diameter and c length equal to the thickness of the bed.
If the iodine reoval efficiency test re:ults are unacceptable, all adsorbent i,) the syste should be replaced. Any EPA filters found defective should be replaced with filters qualified pursuant to Regulatory Position C.3.d of Regulatory Guide *. 52.
Operation of the system every month will deonstrate operability of
(
the filtars and adsorcer system. Operation for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> is used to reduce the moistu:e bu!1d up on thie adsorbent.
If painting, fire, or chemical Talosse occurs such that the HEPA filter or charcoal adsorber could become contaminated from the fLaes, chenicals or foreign materials, the same tests and sample analysis should be perfomed as requitec' for operor.ional use.
Demonstration of the autenatic initiation capabl*tity is necessary to assure syste perfomance capability.
3.7-39 Atendment flo.124 c
se neouq'o UNITED STATES g
8 NUCLEAR REGULATORY COMMISSION o
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- ,I wAswiNoTON, D. C. 20555
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CECCGIA POUER COMPANY OGL_ETHORPE POWER CORPORATION MUNICIPAL ELECTRI_C AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 l
ECulN I. IIATCH NUCLEAR PLANT, UNIT N0. 2 Al'ENDf!ENT TO FACILITY OPERATING LI_ CENSE Amendment No. 62 License No NPF-5 1.
The huclear Regulatory Consission (the Commission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(the licensee) dated December 21, 1983 as modified by letter dated April 16, 1984, 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 Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assu:ance (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 Commission's reg lations; D.
The issuance of this emendment will not be irimical 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.
2.
Accordingly, the license is amended by changes to the Technical Spacifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NFP-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. 62, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license anendment is effective as of its date of issuance and shall be implerented within 60 days.
FOR Tile fiUCLEAR REGULATORY COPf1ISSION Nrw/
kg Daniel R. liuller, Director BWR Project Directorate #2 Division of BWR Licensing I
Attachrcent:
Changes to the Technical j
Specifications j
Date of Issuance: March 26,1986 l
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ATTACHMENT TO LICENSE AMEN 0 MENT NO. 62 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove Insert 3/4 3-54 3/4 3-54 i
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TARI.E 3.3.6.4-1 POST-ACCIEDff NONITORI'E INSTRtSENI% TION
- 1 NINi>IDI p
ON4 Nils bj Iris 1ut ANT Ot*t34AM.E n
n
- 1. Reactor Vessel Pressure'(2821-R623 A, B) 2 u
- 2. ke. actor Vessel. Shroud Water Level {2821-R610, 23,21-R615) 2
- 3. sappasssion n==har Water Level (2148-R622 A, 8) 2
- 4. Sippressloss t't=Ler Water Temperature (ZT47-d626, 2T47-R627) 2
5..Drywe!! Pressure (2T48-R608, 2T48-3609) 2 l'
- 7. Dayw11 Temperature (IT47-R626, 2T47-R627) 2 i
- 8. Ibst-IDCA Gamma Radiation (2D11-E622 A, R C, D) '
2
- 9. tiry m l1 11 -02 Analyzer (2P33-2601 A. R) 2*
l 2
- 10. a) Safety /Reilef Valve Position Primary Indicator (2221-N30I A-Il asal K-M)
(m)
L) S.afety/RcIlef ialve Position Secondary ladicator (2521-N004 A-II anJ K-M)
(a)
Eg II. Daywell liigli Range Pres.aare (2T48-R601 A, 3) 2 i-g
- 12. DryucIl Illgia Ra:Ce Radiation (2D11-E621 A. R, 2T48-R601A, B) 2 (b)
- 13. Stain Stack Post-AcclJent Effluent Mwiltor (Dil-R631)
I (b)(c) mL I4. seactor Rulldisig Vent Flesman Post-Ac:Ident Effluent haltor (2Dil-R631) 1 (l.)(c) 8 t
y t
- The Drywell H 022 Analyzers shall be operable with continuous sampling capability wittiin 30 minutes of an ECCS actuation during a LOCA.
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