ML20092J623
| ML20092J623 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/20/1984 |
| From: | Rivenbark G Office of Nuclear Reactor Regulation |
| To: | City of Dalton, GA, Georgia Power Co, Municipal Electric Authority of Georgia, Oglethorpe Power Corp |
| Shared Package | |
| ML20092J630 | List: |
| References | |
| DPR-57-A-100, NPF-05-A-037, TAC 48120 NUDOCS 8406260543 | |
| Download: ML20092J623 (11) | |
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9 UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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.E WASHINGTON, D. C. 20555 GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR FLANT, UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.100 License No. DPR-57 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applications for amendment by Georgia Power Company, et al.,
(the licensee) dated March 10, 1982 and June 11, 1982, comply 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 applications, the provisions of the Act, ar.d the rules and regulations of the Ccmission; C.
There is reascneble assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and i
safety of the public, and (ii) that such activities will be conducted 4
in compliance with the Coninission's regulations; D.
The issuance of this amendment will not be inimical to the l
comon 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 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:
8406260543 840620' PDR ADOCK 05000321 P
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. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Araendment No.100, are 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.
FOR THE NUCLEAR REGULATORY COMMISSION z bVY
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George Rivenbark, Acting Chief Operating Reactors Branch No. 4 Division of Licensing 2
Attachment:
Changes to the Technical Specifications Date of Issuance: June 20, 1984 Er -
ATTACHMENT TO LICENSE AMENDMENT N0. 37 FACILITY OPERATING LICENSE NO. OPR-57' DOCKET N0. 50-321 i
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
Remove Insert 3.7-10a 3.7-10a 3.7-11 3.7-11 3.7-13 3.7-13 6-17 6-17 a
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8.
_Shutdnwn Recuirements If Specification 3.7. A cannot be met, an orderly shutdown shall be
-initiated and the reactor shall be I
brought to Hot Shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and shall be in the Cold Shut-down condition within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 8. Standay Gas Treatment System
Doerability Recuirements
- 1. Surveillance When System Doerable A minimum of three (2 of 2 in Unit 1 and 1 of 2 in Unit 2) of the four in-At least once per operating dependent standby gas treatment system -
cycle, not to exceed 18 months, trains shall be operable at all times the following conditions shall when Unit I secondary containment be demonstrated:
integrity is required.
a.
Pressure drop across the With one of the Unit 1 standby gas combined ifPA filters and treatment systems inoperable, for charcoal absorber banks is any reason, Unit I reactor operation less than 6 inches of water and fuel handling and/or handling of at the system design flow casks in the vicinity of the spent rate (+10K, -05).
fuel pools is permissible for a
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period of seven (7) days provided b.
Operability of inlet heater that all active comoonents in the ~
at rated power when tested l
remaining operable standby gas in accorchnce with ANSI treatment systems in each unit N510-1975.
(minimum of 1 in Unit I and 1 in Unit 2) shall be demonstrated to.
c.
Air distribution is uniform be opereble within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, ano within 20% across the daily thereafter.
filter train when tested in accordance with N510-1975.
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j 3.7-10a t
Amendment Nos., 55,$$,99,100
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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 8.
Standby Gas Treatment System 8.
Standby Gas Treatment-System
- 1. Doerability Recuirements (Cont'd) 1.
Surveillance When System Operable (Cont'o)
If the inoperable Unit 1 standby gas treatment system is not made
- d. Automatic initiation of each fully operable within the seven train of the Unit 1 and Unit 2 (7) day period, the Unit 1 reactor standby gas treatment systems, shall be shutdown and placed in the cold shutdown condition within
- e. Manual operability of the by-the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and Unit 1 or pass valve for filter cooling.
Unit 2 fuel handling operations shall be terminated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Unit I reactor operation and Unit 1 or Unit 2 fuel handling shall not be allowed if both of the Unit 1 standby gas treatment systems are inoperable or if both of the Unit 2 standby gas treatment systems are inoperable.
- 3. 7.8. 2 Performance Recuirements 2.
Filter Testing a.
The results of the 'n-place a.
The tests and analysis shall DOP and halogentated hydro-be performed at least once per caroon tests at design operating cycle, not to exceed 18 flows on FEPA filters and months, or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> charcoal absorber banks of system operation, or following shall show 99% DOP removal painting, fire or chanical re-and 99% halogenated hydro-lease in any ventilation zone caroon removal when tested communicating with the system.
In accordance with ANSI N510-1975.
b.
00P testing shall be performed after each complete or partial
~i b.
The results of laboratory replacement of the HEPA filter carDon sample analysis shall bank or Efter any structural show 90V. of radioactive methyl maintenance on the system housing lodine removal when tested l
in accordance with RCT-M16-lT c.
Halogentated hydrocarbon testing (800C, 95% R.H.).
shall be performed after each complete or partial replacement c.
Fans shall be shown to operate of the carcoal absorber bank or within +104 -04 design flow after any structural maintenance when tested in accordance with on the system housing.
ANSI N510-1975.
j d.
Each circuit shall be operated i
with the heaters on at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month.
Amendment Nes. 22, pp, JJ, ##,100 3.7-11
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4.7.C.1. Surveillance While Intecrity Maintained (Cont'd) i
- b. Secondary containment capability to.
maintain a minimum 1/4-inch of water.
vacuum under calm wind ( 5 mph)~
conditions with each filter train flow rate not more than 4000 c fm
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shall be demonstrated at each refueling outage, prior to refueling.
3.7.C.2 Violation of Secondary
- 2. Surveillance After Integrity Violated Containment Integrity 4
a.
Without Hatch-UnSt 1 secon-After a secondary containment viola-dary containment ~1ntegrity, tion is determined the standby gas 4
restore Hatch - Unit 1 se-treatment system will be operated condary containment inte-imediately after the affected zones grity within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />,'or per-are isolated from the remainder of form the following (as appli-the secondary containment. The cable):
ability to maintain the remainder 4
i (1) Suscend irradiated fuel of the secondary containment at and/or fuel cask handling 1/4-inch of water vacuum pressure in the Hatch-Unit 1 se-under calm ( 5 mph) wind conditions condary containment.
shall be confirmed.,
1 i
(2) Be in at.least Hot Shutdown within the nsxt 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and
, meet the Conditions of 3.7.C.1.a within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
~
b.
Without Hatch-Unit 1 seconderf centairment, refer to the follow-ing Hatch-Unit 2 Techrdcal Specification, for LCO's to be i
followed for Hatch-Unit 2:
1 (1) Section 3.6.5.1.
(2) Section 3.9.5.1.
D. Primary Containment Isolation Valves
- 0. Primary Containment Isolation Valves 1.
valves Required to be Operable 1.
Surveillance of Operable Valves During reacter hower operation, Surveillance of the primary con-all primary contairment isolation tainment isolation valves shall be valves' listed in Table,3 7-1 and performed as follows:
all reactor coolant system instru-ment line excess flow check valves a.
At least once per operating shall be operable except as stated cycle the operable isolation in Soecification 3.7.0.2.
valves that are power operated and automatically initiated W
shall be tested for simulated
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automatic initiation and the closure times specified in Table 3.7-1.
r Amendment No. (9, )$ DJ,100 3.7-13
3 ADMINISTRATIVE CONTROL PR0hPT NOTIFICATION WITH WRITTEN FOLLOWlP (Continued) g.
Conditions arising from natural or man-made events that, as a direct result of the event require unit shutdown, operation of safety systems, or other protective measures required by Technical Specifications.
h.
Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses, i.
Performance of structures, systems, or components which requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifications bases; or
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discovery during unit life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.
THIRTY DAY WRITTEN REPORTS 6.9.1.9 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within thirty days of occurrence of the event *.
The written report shall include, as a minimum, a completed copy of a licensee event report ferm.
Information provided on the licensee event report form shall De supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances curroundino the event.
Reactor protection system or engineered safety feature instrument a.
settings which are found to be less conservative than these established by the technical specifications but which 'do not prevent the fulfillment of the furctional requirements of affected
- systems, b.
Conditions leading to operation in a degraded made permitted by a i
limiting condition for operation or plant shutdown required by a limiting condition for cperation.
c.
Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.
- All Type 8 and Type C Leakage Tests (i.e., Local Leak Rate Tests) that fail (i.e., test leakage is such that an LER would be required) during an outage shall be reported per one thirty-day written report and shall be submitted within 30 days of the end of such an outage.
Amendment No. $5,100 6-17 L
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION f
GEORGIA POWER COMPANY OGLETHORPE POWER CORP WATION MUNICIPAL' ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET N0. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT N0. 2
-AMENDMENT TO FACILITY OPERATING LICENSE Amendment N3. 37 License No. NPF-5 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Georgia Power Company, et al.,
(thelicensee)datedMarch 10, 1982, 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 (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;.
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
- 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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2)~of Facility Operating License No. NPF-5 is hereby amended to read as follows:
~-1 i.
- Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 37, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
-7m
.fcy.L b l DL-inl&LL Ge'orge W. Rivenbark, Acting Chief Operating Reactors Branch No. 4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: June 20, 1984 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 37 FACILITY OPERATING LICENSE NO. NPF-5 00CKET NO. 50-366 Replace the following page 6.16 of the Appendix "A" Technical Specifications with the enclosed page 6-16.
The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
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ADMINISTRATIVE CONTROL PROMPT NOTIFICATION WITH WRITTEN FOLLOWIP (Continued) g.
Conditions arising from natural or man-made events that, as a direct result of the event require unit shutdown, operation of safety systems, or other protective measures required by Technical Specifications.
h.
Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.
1.
Performance of structures,. systems, or components which requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifications bases; or discovery during unit life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.
THIRTY DAY WRITTEN REPORTS 6.9.1.9 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within thirty days of accurrence of the event *.
completed copy of a licensee event report form.The written report shall include, a Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.
Reactor protection system or engineered safety feature instrument a.
settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems.
b.
Conditions leading to operation in a degraded made permitted by a l
limiting condition for operation or plant shutdown required by a l
limiting condition for operation.
Observed inadequacies in the implementation of administrative or c.
procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems.
- All Type 8 and Type C Leakage Tests (i.e., Local Leak Rate Tests) that fail (i.e., test leakage is such that an LER would be-required) during an outage shall be reported per one thirty-day written report and shall be submitted within 30 days of the end of such an outage.
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Amendment No. 37 6-16
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