ML20079P919
| ML20079P919 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/01/1991 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079P923 | List: |
| References | |
| GL-88-01, GL-88-1, NUDOCS 9111140164 | |
| Download: ML20079P919 (13) | |
Text
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o, UNITED STATES NUCLE AR REGULATORY COMMISSION f
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WASHINGT ON. D. C. 20555 GEORGIA POWER COMPANY i
OGLETHORPE POWER CORPORATION l
MilNICIPAL ELECTRIC AllTHORITY OF GEORGIA CITY OF DAl. TON, GEORGIA DOCKET,NO. 50 321 EDWlH 1. HATCH NI! CLEAR PLANT, littlT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 176 License No. DPR-57 1.
The Nuclear Regulatory Comission (the Commission) has found that:
The app (lication for amendment to the Edwin 1. Hatch Nuclear Plant.the fac A.
Unit 1 Georgia Power Company, acting for itself Oglethorpe Power Corporation, Municipt1 Electric Authority of Georgia, and City of Dalton, 1
l Georgia (the licensees) dated April 12, 1991, complies with the standaris and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Combsion's rules and regulations set forth in 10 CFR Chapter I; l
fl.
The facility will operata 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 Le conducted in compliance with the Cornission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this license amendment will not be inimical to the comon defense and security er to the health and safety of the public; and E.
The issuance of tiih ateadment is in accordance with 10 CFR Part 51 of the Comission's "4plations and all applicable requirements have been satisfied.
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1 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. OPR-57 is hereby amended to read as follows:
Technical Specifications The Technical Specificatiens contained in Appendices A and B, as revised through Amendment tio.176, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective within 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMiilSSION l )}lC k+%tQ al David B. Matthews, Directo Project Directorate 11-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of issuance:
November 1. 1991
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ATTACHMENT TO LICENSE AMENDMENT HO. 176 FACILITY OPERATING LICENSE NO. OPR-57 DOCKET HO. 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 indicatina the areas of change.
Remove pages Insert pages 3.6-7 3.6-7 3.6-8 3.G-8 3.6-10 3.6-10 n
LIMlilNG CONDITIONS FOR OPERAfl0N 50RvillLAN Q R[OVlRIMENTS 3.6.F.2.c.
When the time limits or maxi-4.6.F.2.c.3.
Primary coolant pH shall mum conductivity or chloride be nicesured at least once concentration limits are ex-every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> whenever ceeded, an orderly shutdown reactor coolant condut-shall be initiated and the tivity is > 2.0pmho/cm rcettor shall be in the Cold at 25'C.
Shutdown Condition withif. 24
- hours, d.
Whenever the reactor is not pressurized, a sample of the reactor coolant shall be analyrea at least every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> for chloride ion content and pH.
G.
Reactor Ceplant Leakaat*
6.
Reactor Coolant Leakene 1.
Unidentified and Total Unidentified sources of reactor Any time irradiated fuel is in coolant system leakage shall be the reactor vessel and reactor checked by the drywell floor coolant temperature is above drain sump system and 212*F:
recorded at least once per 8 l
hours. Identified sources of a.
reactor coolant system leak-reactor coolant system age into the primary contain-leakage shall be checked by ment from unidentified sources the equipment drain sump shall not exceed 5 gpm; system and recorded at least orge per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The readings l
b.
reattor coolant system leakage provided by the primary into the primary containment containment atmosphere f rom unidentified sources particulate radioactivity shall not increase more than monitoring system, the 2 gpm within a 24-hour primary containment radio-period or less; and iodine monitoring system, and the primary containment c.
the total reactor coolant sys-gaseous radioactivity tem leakage into the primary monitorita system shall containment shall not exceec also be recorded at least 25 gpm within any 24-hour l
once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
l
- period, wnen checked in accordance with 4.6.G.
2.
Leakane Detection Systems a.
At least one of the leakage measurement instruments assoc-isted vith each sump shall be operable and two of the other.
three leakage detection systems identified in Table 3.2-10, note e shall be operable when irradiated fuel is "Not required during performance of an inservice hydrobtatic or leakage test even if reactor coolant temperature is above 212'F.
HATCH - UNIT 1 3.6-7 Amendment No. 176 n
(IMlflhG CON 0lflON$ f 0R Orf RA110N suRvilitANtt alDblR(MINTS G.
Reactor foolant teakaot j
2.
teshace Detection Systems itent'd) 4.
(Continued)
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in the reactor vessel and reactor coolant temperature is above 212'F. Further, the primary containment atmosphere particulate radioattivity monitoring system shall be among these two operable systems, or samples shall be cotained and denlyzed at least once each B hours.
l b,
From and af ter the date that eny two of the f our systems identified in Table 3.2*10.
note c are made or found to be inoperable, but with the primary containment atmosph re particulate radioactivity monitoring system operable, reactor power operation may continue for the sbcceeding 30 days provided the primary containment atmosphere particulate radioactivity monitoring system reading is checked and recorded at least once each 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
l c,.From and af ter the date that any two of the four systems, including the primary containment atmosphere particulate radioactivity monitoring system, identified in Table 3.2-10, note c are.
made or found to be inoperable, resctor power operation may continue f or the succeeding 30 days provided samples of the containment atmosphere are obtained and analyzed at least once each 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
l e
HATCH - QNii 1 3.6-8 Amendment No. 176 n
LlrITING CONDITICNS 6 0k Of[k A110N SUEvfittAhCE Rt0VIR[M'NT5 3.6.K.
STRtittVRat INifGRl h a.6.K.
STRUCTUDat INftGRITY 1.
Nomal Cenoition Surveillance Reautrements for in-service inspection and testing of A5kl Code the structural integrity of A5ME Class 1, 2. and 3 (equivalent) components Code Class 1, 2, and 3 (eoviva-shall be applicable as follows:
lent) components shall be maintained in accordance with the 1.
In-service inspection of A5ME Surveillante Requirements of Code Cl?ss 1, 2 and 3 (equivalent)
Specification a.6.K.
components and in-serivte testing of ASMt Code Class 1, 2, and 3 2.
Off-Normal (qnditions (equivalent) pumps and valves shall be perf omed in accordance with e.
With the structural Section Al of the A5ME Boiler ord integrity of any ASME Code Pressure vessel (cde and applicable Class I component not Addenda as required by 10Cf R$0, conf oming to the above Section 50.55a(g), encept where requirements, restore the specific relief has been structural integrity of granted by the Comission pursuant the affected component (s) to 10CFR50, section 50.55a(g) to within its limit or (6) (1).
isolate the effected component (s) prior to increasing the Reactor 2.
Performance of the above in-service Coolant System tenotrature inspection and testing activities more than 50'F abo,e the shall be in addition to other minimum temperature required specified Surveillance by hD1 considerations.
R*Quirements.
b.
With the structural integrity 3.
Nothing in the A5ME Boiler and of any A5ht Code Class 2 Pressure Vessel Code shall be component (s) not conforming construed to supersede the to the above requirements, requirements of any technical restore the structural Specification.
integrity of the affected component (s) to within its a.
The Intervice Inspection Program limit or isolate the affected for piping identified in NRC component (si prior to Generic Letter 88-01 shall be increasing the Reactor Coolant perf omed in accordance with the System temperature above 212'F.
staff positions on schedule, methods and personnel, and sample c.
With the structural it.tegrity espansion included in the generic of any ASME Code Class 3 letter, except where specific compontnt(s) not contoming to written relief has been granted the above requirements, restore by the Comission, the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) from service.
MATCH - UN!l 1 3.0-10 A
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GEORGIA POWER C0tiPAt4Y OGLETPORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY Oi DALTON, GEORGIA DOCKET NO. 50-366 EDWIN 1. HATCH NUCLEAR PLAllT, Oh1T ?
AliENDfiENT TO FACILITY OPERATING LICENSE Amendn1 No.
11'/
License No. NPF-5 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Edwin 1. Hatch Nuclear Plant, Unit 2 (the facility) Facility Operating License No. NPF-5 filed by Georgio Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees) dated April 12, 1991, 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 it 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 Comission's regulations set forth in " CFR Chapter I; The issuance of this license 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 Comission's regulations and all applicable requirements have been satisfied.
I 1
i 2.
Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendmen+.
and paragraph 2.C.(2) of Facility Operating License No. NPF-5 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.ll7, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective within 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l}
c1 CellCbt
-)]lC O'L'Q r!W David B. Matthews, Director 1
Project Directorate 11-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance:
November 1. 1991 9
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l ATTACHMENT TO LICENSE AMENi' MENT NO. 117 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 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.
Remove Pages hsertPages 3/4 0-2 3/4 0-2 3/4 0-3 3/4 0-3 3/4 4-5 3/4 4-5 3/4 4-6 3/4 4-6 p
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APPLICABILITY SURVf!LLANCE REQUIREMENTS (Continued) b.
A total maximum combined interval time for any 3 consecutive surveillance intervals not to exceed 3.25 times the specified surveillance interval.
4.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the speci.'ication.
Surveillance requirt-ments do not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable state shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the acplicable surveillance interval or as otherwise specified.
4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class I, 2, & 3 components shall be applicable as follows:
a.
Inservice inspection of ASME Code Class I, 2, and 3 components and inservice testing of ASML Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.Section XI 50.55a(g),
except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
b.
Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
HATCH - UNIT 2 3/4 0-2 Amendment No. 117 n____
l l
3/4.0 APPLICABILITY SURVEILLANCE REQUIREMENTS (Contintea)
ASME Soiler anc Pressure Vessel Required frequencies Code and aopil:atie addenca for cerforming inservice terminology for inservice inspection and testing inspection and testing activities activities Weekly At least once per 7 cays Monthly at least once ce' 31 days Quarterly or every 3 'nonths At least once per 92 cays Semiannually or every 6 months At least once per 184 cays fearly or annually At least once ter 366 days T e provisi:ns of Scecift:ation 4.0 2 are applicable to tne h
acove recuires frecuent'e; for cerforming inservice inspection and testing activities.
a.
Performance of the above inservice inspection and testing activities sha'l te in aa;ition to other specified Surveillance Recuirements, e.
Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersece the requirements of any Tecnnical Specification.
f.
The Inservice Inspect *on Program for piping identifled in NRC Generic Letter 88-01 shall be performed in accordance with the staff positions on schedule, methods and personnel, and sample expansion included in the generic letter, except where specific written relief has been granted by the Commission.
9TCH - UNIT 2 3/4.-3 Amendment No. 117
_s__------
RJACTOR COOLANT SYSTEM 3/4.4.3 REACTOR COOLANT SYSTE-.EAKAGE LEAKAGE DETECTION SYSTEMS LIMITING COND7T10N FOR OPERATION 3.4.3.1 The following reactor coolant system leakage detection systems shall be OPERABLE:
a.
The primary containment atmosphere particulate radioactivity monitoring system, b.
The primary containment floor drain and equipment sump level and flow monitoring systems, and c.
The primary Containment gaseou$ radioactivity monitoring system.
APPLICABILITY:
CONDITIONS 1, 2 and 3.
ACTION:
a.
With either the primary containment atmosphere particulate radioattivity monitoring system or the primary containment gaseous radioactivity monitoring system inoperable, operation may continue for 30 days provided grab samples of the containment atmosphere are obtained and analyzed at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; b.
With at least one leakage monitoring instrument OPERABLE for both the primary containment floor drain sump and the equipment sump, operation may continue for 30 days; c.
Otherwise, 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 following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.4.3.1 the leakage detection systems shall be demonstrated OPERABLE by:
a.
Primary containment atmosphere gaseous and particulate monitor-ing system-cerformance of a CHANNEL CHECK at least once per 5 l
hours, a CHANNEL FUNCTIONAL TEST at least once per 31 days and a CHANNEL CAllBRATION at least once per 18 months, b.
Primary containment sump level and flow monitoring system-performance of a sensor check at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, l
CHANNEL FUNCTIONAL TEST at least once per 31 deys and a CHANNEL CAllBRATION at least once per 18 months.
HATCH - UNIT 2 3/4 4-5 Amendment No. 117
_______-____--_____-_-_--__-_____-___________-_-___t____
REACTOR CDDLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:
a.
No PRESSURE BOUNDARY LEAKAGE, b.
5 gpm UNIDENTIFIED LEAKAGE, c.
25 gpm total leakage averaged over any 24-hour period, and d.
2 gpm increase in UNIDENTIFIFD LEAKAGE within a 24-hour period or less.
APPLICABILITY: CONDITIONS 1, 2 and 3.
ACTION:
a.
With any PRES 50pr INDARY LEAKAGE, be in at least HOT SHUT-DOWN within 12 hou.. and in COLD SHUTDOHN within the next 24
- hours, b.
With any reactor coolant system leakage greater than the limits specifically in b or c above, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> cr 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 following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
With any reactor coolant system leakage greater than the limits specified in d above, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-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 follos.**ng 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS
\\
4.4.3.2 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by; a.
Monitoring the primary containment floor drain sump and equip-ment sump levels and flow rates at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and l
b.
Monitoring the primary containment atmospheric particulate and gaseous radioactivity at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
HATCH - UNIT 2 3/4 4-6 Amendment No, 117 L
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