ML20134H669
| ML20134H669 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 11/12/1996 |
| From: | Shiraki C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20134H660 | List: |
| References | |
| RTR-REGGD-01.163, RTR-REGGD-1.163 NUDOCS 9611140218 | |
| Download: ML20134H669 (11) | |
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p UN!TED STATES g
j NUCLEAR REGULATORY COMMISSION J
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P WASHINGTON, D.C. 20006 4 001 o%...../
COMMONWEALTH EDISON COMPANY l
DOCKET NO. 50-295 l
l ZION NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No. 175 License No. DPR-39 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The pplication for amendment by Commonwealth Edison Company (the l
licensee) dated August 29, 1996, as supplemented on September 20, 1996, and October 4, 1996, 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; C.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the j
Commission; C.
TF.ere is reasonable assurance (i) that the activities authorized l
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be l
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 l
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating Licens: No. OPR-39 is hereby amended to read as follows:
9611140218 961112 PDR ADOCK 05000295 P
. t (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
175, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is offective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION ed,
Clyde Y. Shiraki, Senior Project Manager Project Directorate III-2 i
Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Chatiges to the Technical i
Specifications Date of Issuance: November 12, 1996 1
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p e ttro g
t UNITED STATES NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 30666-4001
.....p COMONWEALTH EDISON COMPANY DOCKET NO. 50-304 ZION NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.162 License No. DPR-48 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated August 29, 1996, as supplemented on September 20, 1996, and October 4, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Ca nission's rules and regulations set forth in i
10 CFR Ct,aptu I; 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 I
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be l
conducted in compliance with the Commissiin'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-48 is hereby amended to read as follows:
. (2)
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
162, 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 the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
\\
Clyde Y. Shiraki, Senior Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 12, 1996 i
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ATTACHMENT TO LICENSE AMENDMENT NOS. 175 AND 169 FACILITY OPERATING LICENSE N05. DPR-39 AND DPR-48 DOCKET NOS. 50-295 AND 50-304 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
Remove Paaes Insert Paaes 212 212 213 213 214 214 214a 214a 214b 214b 326a l
LINITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.10 CONTAllMENT STRUCTURAL INTEGRITY (per unit) 4.10 CONTAINMENT STRUCTURAL INTEGRITY foer unit) i OBJECTIVE:
OBJECTIVE:
To insure that the containment structure meets To establish the testing requirements to assure I
its design r6quirements throughout plant life.
containment structural integrity.
SPECIFICATION:
1.
Containment Leakage Rate Testing 1.
Containment Leakage Rate Testing A.
Surveillance and testing of the A.
Containment Leakage Rate shall be containment shall be perfomed as limited to:
follows:
1.
An overall integrated leakage 1.
The containment Type A leakage rate less than or equal to that rate shall be determined in specified by the Containment accordance with the Containment Leakage Rate Testing Program.
Leakage Rate Testing Program.
l 2.
A combined leakage rate less than or equal to that specified l
by the Containment Leakage Rate Testing Program, for all i
penetrations and valves subject i
to Type B and C tests, when pressurized to P,.
APPLICABILITY: Modes 1, 2, 3, 4 and 7 l
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212 Amendments Nos. 175 and 162 I
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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT l
3.10.1.A (Continued) 4.10.1.A.2.
Type B and C tests (except air lock tests) shall be performed in accordance ACTION:
with that specified by the Containment Leakage Rate Testing Program.
With either (a) the measured overall integrated containment leakage rate, or (b) the measured 3.
Air locks shall be tested and combined leakage rate for all penetrations and demonstrated OPERABLE per Surveillance valves subject to Type B and C tests exceeding that Requirement 4.10.2.
specified by the Containment Leakage Rate Testing Program, restore the applicable leakage rate to less 4.
Type A, B, and C leakage rate tests l
than or equal to that specified by the Containment shall be considered to be satisfactory i
Leakage Rate Testing Program prior to entering if the acceptance criteria delineated by MODE 4.
the Containment Leakage Rate Testing Program are met.
5.
Leakage from containment isolation valves sealed by the Isolation Valve Seal Water system may be excluded from the combined Type B and C leakage rate.
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213 Amendment Nos. 175 and 152
LINITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.10.1.A (Continued) 4.10.1.A.6.
The retest schedules for Type A, B, and C l
tests shall be in accordance with the Containment Leakage Rate Testing Program.
l 7.
Inspection and reporting of tests shall be in accordance with the Containment Leakage Rate Testing Program.
1 214 Amendment Nos.175 and 162
LIMITING CONDITION'FOR OPERATION SURVEILLANCE REQUIREMENT 3.10.2.
Containment Air Locks 4.10.2.
Containment Air Locks A.
Each containment air lock shall be A. Each air lock shall be demonstrated OPERABLE:
OPERABLE with:
1.
Both doors closed 3xcept when the air Verify that the overall air lock leakage rate, lock is being used for normal entry and the leakage rate for each door, are less and exit through the containment, then than or equal to that specified by the at least one air lock door shall be Containment Leakage Rate Testing Program.
closed, and Verifications shall be conducted at the 2.
The air lock leakage rate shall be frequency specified by the Containment Leakage less than or equal to that specified Rate Testing Program.
by the Containment Leakage Rate Testing Program.
APPLICABILITY: Modes 1, 2, 3, 4 and 7 ACTION:
a.) With one containment air lock door inoperable:
1.
Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE 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 air lock door closed.
2.
Operation may continue until performance of the next required overall air lock leakage test provided that the OPERABLE air lock door is verified locked closed at least once per 31 days, 3.
Otherwise be in at least MODE 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 5 within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
214a Ame idment Nos.175 and 162
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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT s 3.10.2 (Continued)
At least once per 6 months by verifying that only one door in each air lock can be opened at 4.
The provisions of Technical a time.
Specification 3.0.4 are not applicable.
b.) With the containment air lock inoperable, except as a result of an inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE statu>
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 MODE 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in MODE 5 within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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214b Amendment Nos. 175 and 162 l
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6.10 Containment Leakaae Rate Testina Proaram 1.
A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR Part 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leakage Test Program" dated September 1995, with the following exception:
Section 10.2.1 of NEI 94-01, Revision 0, is not applicable to Unit 1 penetration P-16.
This exception i
for penetration P-16 shall expire at the completion of Unit 1 outage ZlR15.
2.
The peak ca'lculated containment internal pressure for the design basis loss of coolant accident, P,, is 46.79 psig. The containment design pressure is 47 psig.
3.
The maximum allowable containment leakage rate, L, at P,, shall be s0.1% of containment air weight per day.
4.
Leakage rate acceptance criteria are:
a.
Containment leakage rate acceptance criterion is $1.0 L. During the first unit startup following testing in accordance with this program, the leakage raIe acceptance criteria are <0.60 L, for the Type B and C tests and <0.75 L, for the Type A tests b.
Air lock testing acceptance criteria are:
1)
Overall air lock leakage is 50.6 L, when combined with all Type B and C test results at a test pressure of 2 P,.
2)
For each door, leakage rate is 51.0 SCFH when tested at 22.5 psig and <10 psig, or $4.75 SCFH when tested at 210 psig.
5.
The provisions of Surveillance Requirement 4.0.2 do not apply to the test frequencies specified in the i
Containment Leakage Rate Testing Program.
6.
The provisions of Surveillance Requirement 4.0.3 are applicable to the Containment Leakage Rate Testing Program.
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326a Amendment Nos. 175 and 162
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