ML20245G409
| ML20245G409 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/20/1989 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245G414 | List: |
| References | |
| NUDOCS 8906290132 | |
| Download: ML20245G409 (24) | |
Text
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fg UNITED STATES l
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555 k.....,/
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN 1. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 164 License No. DPR-57 1.
The Nuclear Regulatory Columission (the Comission) has found that:
The app (lication for amendment to the Edwin I. 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, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensee) dated February 3,1989, 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 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 set forth in 10 CFR Chapter 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 r cordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied, h
AODN P
. 1 2.
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 l
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.164, 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 issurac.e and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION BW David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 20,1989 i
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m.
.. 2.
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. 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.101, are hereby incorporated in the p
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 Griginal Signed By:
David B. Mat; hews David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regul.ation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 20,1989 0FFICIAL RECORD C0P' A:
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ATTACHMENT TO LICENSE AMENDMENT NO. 164 FACILITY OPERATING LICENSE N0. 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 amendrent number and contain vertical lines indicating tbe area of change.
Remove Page Intert Page 3.7-6 3.7-6 3.7-6a 3.7-6a 3.7-16 3.7-16 3.7-18 3.7-18 3.7-18a 3.7-18a 3.7-18b 3.7-18b 3.7-21 3.7-21 3.7-26a 3.7-26a 3.7-27 3.7-27
V t_IMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.7.A.2.e.
Tvos 8 Tests - Leak Tests of Pent-trations with Seals and Bellows (Continued) (Tables 3.7-2 and 3.7-3)
(1)
Primary containment components which seal or penetrate the pressure containing boundary of the containment.shall be tested at a pressure not less than Pa.
These components shall be tested at each major refueling shutdown or at intervals not to exceed 2 yea rs.
(2) (a) The primary containment airlock shall be tested at 6-month intervals at P by a
pressurizing the compart-ment between the two air-lock doors. The leakage shall not exceed 0.05 L
- a (b) If the primary containment airlock is opened during periods when primary contain-ment integrity is not required, the test required by 4.7 A.2.e.(2)(a) shall.
be performed at the end of such periods.
(c) If the primary containment airlock is opened during periods when primary contain-ment integrity is required, it shall be tested within 3 days of being opened by pressurizing the gap between the door seals to 1 10 psig for at least 15 minutes. The leakage for each set of door seals shall not (xceed 0.01 L-a (d) If primary containment is required and the primary containment airlock is being opened more frequently than once every 3 days, the test required by 4.7.A.2.e.(2)(c) shall be performed at least once per 3 days during the period of frequent openings.
- 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 snall be reported according to 10 CFR 50.73 by one, 30-day written report that is due within 30 days of the first leakage test failure in the outage.
All other leakage test failures discovered during the outage will be reported in a revision to the original report due within 30 days after the end of the outage.
s
/bnendnXH1t No. 164 HATCH - UNIT 1 3.7-6 m-
_-___m____
LIMITING CONPITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
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(e) At least once per 6 months it shall be verified that only one door in the air-lock can be opened at a time.
f.
Ivoe C Tests-Local Leak Tests of Containment Isolation valves (Tables 3.7-1 and 3.7-4)
Type C tests shall be performed under the program established in Appendix J of 10 CFR Part 50.
Containment isolation valves (except for main Jteam line iso-lation valves) shall be tested at a pressure not less than P
- a Type C tests shall be performed at each major refueling shutdown or at intervals not to exceed 2 years.*
g.
Acceptance Criteria for Tvoe B and Tvoe C Tests The combined leakage rate of c naonents subject to Type B and C tests shall be determined under the program established in Appendix J of 10 CFR Part 50 and shall not exceed 0.6 L
- a h.
Main Steam Line Isolation Valves The main steam line isola-tion valves shall be tested at a pressure of 28 psig for leakage at least once per operating cycle. If a total leak rate of 11.5 scf per hour for any one main steam line isolation valve is exceeded, repairs and retest shall be performed to correct this condition.
l "All Type B 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 according to 10 CFR 50.73 by one, 30-day written report that is due within 30 days of the first leakage test failure in the outage.
All other leakage test failures discovered during the outage will be reported in a revision to the original report due within 3G days af ter the end of the outage.
HATCH - UNIT 1 3.7-6a k7endnent No. 164 4
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Table 3.7-2 Testable Penetrations with Double 0-Ring Seals 2
i Penetration No.
Penetration Description g
X-1 A&8 Equipment Hatch (1) (2) (4) (6) c X-2 Personnel Lock (1) (4) (7) (g)
X-4 Head Access Hatch (1) (2) (4) (6)
X-6 CR0 Removal Hatch (1) (2) (4) (6)
X-35-A through TIP System (1) (2) (4) (6)
X-35-E X-43 Drywell Test (1) (2) (4) (6)
X-200 A,B,6C Suppression Chamber (1) (2) (4) (6)
Access Manhole X-218 8 Construction Drain (1) (2) (4) (6) l HATCH - UNii 1 3.7-21 Amendnent No. 164
ci -
Table 3.7-4 (Continued)
Primary Containment Testable Isolation Valves Penetration.
Number Valve Designation h
'X-2118 E11-F0278 & E11-F0288 (1) (2) (4) (5) (9)
X-217 P33-F007 & F015 (1) (2) (4).(5) (9)
\\
HATCH - UNIT 1 3.7-26a Amendment !!o.164 m
___:m__.-m_---
Notes For Tables 3.7-2 th.,uch 3.s,
l (1) Test duration for all valves and penetrations listed will generally exceed I hour.
1 (2) Test pressures are at least $9 psig for all valves and penetrations
)
except MSIVs which are tested at 28 psig.
W"'t (3) MSIV accept'able leakage limit is 11.5 scfh/ valve of air.
(4) The total acceptable leakage for all valves and penetrations other than the MSIVs is 0.6 L -
a (5) Local leak tests on all testable isolation valves shall be perfonned each major refueling shutdown bt.t in no case at intervals greater than 2 j
years.
j
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(6) Local leak tests on all testable penetrations shall be performed each
{
trajor refueling shutdown but in no case at intervals greater than 2 j
years.
(7) The personnel airlock shall be tested at intervals not to exceed 6 months.
l l
(8) The personnel airlock door seals are tested at 10 psig per i
4.7.A.2.e.(2)(c) and 4.7.A.2.e.(2)(d).
(9) Identifies isolation valves that are tested by applying pressure between the inboard and outboard isolation valves.
Ir. board valve is not tested in the direction required for isolation but will have equivalent or more conservative leakage results.
(10) Identifies isolation valves that are tested by applying pressure between
.the isolation valve and a manually operated valve such that the isolation valve is tested in the direction required for isolation.
(11) Identifies isolation valves that are tested by applying pressure between the isolation valves and other system valves. Isolation valves not tested in the direction required for isolation will have equivalent or more conservative results.
(12) The RHR system remains water filled post-LOCA. Isolation valves are tested with water.
(13) Identified blind flange that is tested by applying pressure between the flange and a manually operated valve such that the flange is tested in the direction required for isolation.
(14) Identifies isolation valves that are tested by applying pressure between l
the inboard and outboard isolation valves.
i l
HATCH - UNIT 1 3.7-27 Anondnent flo.164 l
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UNITED STATES NUCLEAR REGULATORY COMMISSION r,
!j WASHINGTON, D. C. 20555
%,...../
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA l
CITY OF DALTON, GEORGIA j
1 DOCKET NO. 50-366 EDWIN 1. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.101 License No. NPF-5 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 2 (the facility) Facility Operating License No. NPF-5 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 3,1989, 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 ir. 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 aut?,rized 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 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.
l l
C
. 2.
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. 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.101, 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 and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION David B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Speci fications Date of Issuance: June 20, 1989 l
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2.
Accordingly, the license is amended'b,y changes to the Technical Specifi-cations as-indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operatino 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.164, 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-and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By:
David B. Matthews.
David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical
. Specifications Date of' Issuance:
June 20, 1989 I
0FFICIAL RECORD M
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ATTACHMENT TO LICENSE AMENDMENT NO.101 FACILITY OPERATING LICENSE N0. 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 anwndment number and
.i contain vertical lines indicating the area of change.
Remove Page Insert Page 3/4 6-3 3/4 6-3 3/4 6-6 3/4 6-6 3/4 6-17 3/4 6-17 3/4 6-18 3/4 6-18 3/4 6-20 3/4 6-20 3/4 6-21 3/4 6-21 3/4 6-22 3/4 6-22 I
)
'h
l CONTAINMENT SYSTEMS PRIMARY CONTAINMENT LEAKAGE l
_ LIMITING CONDITION FOR OPERATION 3.6.1.2 Primary containment leakage rates shall be limited to:
An overall integrated leakage rate of:
a.
1.
s L, 1.2 percent by weight of the containment air per 24 a
hours at P, 57.5 psig, or a
2.
s L, 0.849 percent by weight of the containment air per 24hoursatareducedpressureofp,28.8psig.
t b.
A combined leakage rate of:
1.
s 0.60 La for all penetrations and valves, except for main steam isolation valves, subject to Type B and C tests when pressurized to P, and a
2.
s 0.009 La for the following penetrations *:
(a)
Main steam condensate drain, penetration 8; (b)
Deleted l
(c)
Reactor water cleanup, penetration 14; (d)
Equipment drain sump discharge, penetration 18; (e)
Floor drain sump discharge, penetration 19; and (f)
Chemical drain sump discharge, penetration 55; i
(g)
Deleted l
11.5 scf per hour for any one main steam isolation valve when c.
tested at 28.8 psig.**
APPLICABILITY: When PRIMARY CONTAINMENT INTEGRITY is required per Spec 1fication 3.6.1.1.
- Potential bypass leakage paths.
- Exemption to Appendix J of 10 CFR 50.
HATCH - UNIT 2 3/4 6-3 Anendnent "lo.101
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCK LIMITING CONDITION FOR OPERATION 3.6.1.3 The primary containment airlock shall be OPERABLE with:
Both doors closed except when the airlock is being used for a.
normal transit entry and exit through the containment, then at least one airlock door shall be closed, and b.
An overall airlock leakage rate of s 0.05 La at P. 57.5 psig.
a APPLICABILITY: CONDITIONS 1, 2* and 3.
ACTION:
With one primary containment airlock door inoperable, maintain at a.
least the OPERABLE airlock door closed; restore the inoperable airlock door to CPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or lock the OPERABLE airlock door closed; operation may then continue until performance of the next required overall airlock leakage test provided that the OPERABLE air':ck door is verified to be locked closed at least once per 30 days. The provisions of Specification 3.0.4 are not applicable.
b.
With the primary containment airlock inoperable, except as a result of an inoperable airlock door, maintain at least one airlock door closed; restore the inoperable airlock to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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 c.
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 4.6.1.3 The primary containment airlock shall be demonstrated OPERABLE:
The primary containment airlock shall be tested at 6-month a.
intervals at pa by pressurizing the compartment between the two airlock doors. The leakage shall not exceed 0.05 La-b.
If the primary containment airlock is opered during periods when primary containment integrity is not required, the test required by 4.6.1.3.a. shall be performed at the end of such periods.
If the primary containment airlock is opened during periods when c.
primary containment integrity is required, it shall be tested within 3 days of being opened by pressurizing the gap between the doors seals to 210 psig for at least 15 minutes. The leakage for each set of doors seals shall not exceed 0.01 La-d.
If prirrary containment is required and the primary containment airlock is being opened more frecuently than once every 3 days, the test required by 4.6.1.3.c. shall be performed at least once per 3 days during the period of frequent openings.
At least once per 6 months by verifying that only ore door in l
o.
the airlock can be opened at a time.
- See Special Test Exception 3.10.1.
l HATCH - UNIT 2 3/4 6-6 Amendment No.101 l
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