ML20155H589
| ML20155H589 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 11/06/1998 |
| From: | Clifford J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20155H591 | List: |
| References | |
| NUDOCS 9811100201 | |
| Download: ML20155H589 (16) | |
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UNITED STATES s
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 2006HOM
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SOUTHERN CAllFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CALIFORNIA THE CITY OF ANAHE!M. CAllFORNIA DOCKET NO.60-361 SAN ONOFRE NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.144 License No. NPF-10 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern California Edison Company, et al.
(SCE or the licensee) dated May 11,1998, as supplemented by letter dated October 9,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 (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 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.
9811100201 981106 PDR ADOCK 05000361 P
! 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-10 is hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specificatioris contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
144, are hereby incorporated in the license. Southern Califomia Edison Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance to be implemented within 30 days from the date ofissuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
h James W. Clifford, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
November 6, 1998
_.__________-a
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.144 TO FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 l
i Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT 3.6-2 3.6-2 3.6-6 3.6-6 3.6-14 3.6-1A 5.0-20a 5.0-20s 5.0-20b i
.._. =
Containment 3.6.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1 Perform required visual examinations and In accordance leakage rate testing except for containment with the air lock testing, in accordance with the Containment Containment Leakage Rate Testing Program.
Leakage Rate Testing Program SR 3.6.1.2 Verify containment structural integrity In accordance in accordance with the Containment Tendon with the Surveillance Program.
Containment Tendon Surveillance Program f
SAN ON0FRE--UNIT 2-3.6-2 Amendment No. 127,144
Containment Air Locks 3.6.2 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME
' D.
Required Action and D.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.
AHQ D.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1
NOTES-------------------
1.
An inoperable air lock door does not 3
invalidate the previous successful performance of the overall air lock leakage test.
2.
Results shall be evaluated against acceptance criteria applicable to SR 3.6.1.1.
Perform required air lock leakage rate In accordance testing in accordance with the Containment with the Leakage Rate Testing Program.
Containment Leakage Rate r
Testing Program (continued)
SAN ONOFRE--UNIT 2 3.6-6 Amendment No. 127,144
Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)
~-
SURVEILLANCE FREQUENCY SR 3. 6. 3. 4 - - - - -- - - - - - - - - - - - - N O T E S - - - - - - - - - - -- - - - - - - - -
'1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.
- 2. SR 3.0.4 is not applicable.
Verify each containment isolation manual valve Prior to and blind flange that is located inside entering MODE 4 containment and required to be closed during from MODE 5 if accident conditions is closed, except for not performed containment isolation valves that are open within the under administrative controls.
previous 92 days SR 3.6.3.5 Verify the isolation time of each Section A In accordance and B power operated and each automatic with the containment isolation valve is within limits.
Inservice Testing Program 4
SR 3. 6. 3. 6 - - - - - - - - - - - - - - - - - - N OT E S - - - - - - - - - - - - - - - - - - - - -
Results shall be evaluated against acceptance criteria applicable to SR 3.6.1.1.
Perform leakage rate testing for containment 184 days purge valves with resilient seals.
8_@
Within 92 days after opening the valve (continued)
SAN ONOFRE--UNIT 2 3.6-14 Amendment No. 127,144
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) 5.5.2.14 ConfigurationRiskManagementProgram(CRMP)
(Continued) d.
Provisions for assessing the need for additional actions after the discovery of additional equipment out of service conditions while in the LC0 Condition.
e.
Provisions for considering other applicable risk significant contributors such as Level 2 issues, and external events, qualitatively or quantitatively.
5.5.2.15 Containment Leakage Rate Testing Program 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 50, Appendix J, Option B, as modified by approved exemptions. This arogram shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995.
The calculated peak containment internal pressure related to the design basis loss-of-coolant accident, P., he calculated pe kis 55.1 psig (P w conservatively be assumed to be equal to t a
containment internal pressure for the design basis Main Steam Line Break (56.6 psig) for the purpose of containment testing in accordance with this Technical Specification).
The maximum allowable containment leakage rate, L., at P., shall be 0.10% of containment air weight per day.
Leakage rate acceptance criteria are:
a.
The Containment overall leakage rate acce)tance criterion is s 1.0 L During the first unit startup following testing in accordan,.ce with this program, the leakage rate acceptance criteria are s 0.60 L, A tests;for the Type B and Type C tests and s 0.75 L, for the Type b.
Air lock testing acceptance criteria are:
1)
Overall air lock leakage rate is s 0.05 L, when tested at 2 P,.
2)
For each acor, the leakage rate is s 0.01 L, when pressurized to a 9.0 psig.
SAN ON0FRE--UNIT 2 5.0-20a Amendment No. 127d 39,144
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs,andManuals(continued) 5.5.2.15 Containment Leakage Rate Testing Program (Continued)
The provisions of Surveillance Requirement 3.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program. However, test frequencies specified in this Program may be extended consistent with the guidance provided in NEI 94-01,
" Industry Guideline For Implementing Performance-Based Option Of l
10CFR 50, Appendix J," as endorsed by Regulatory Guide 1.163.
Specifically, NEI 94-01 has these provisions for test frequencies extension:
2.
Consistent with standard scheduling practices for Technical i
Specifications Required Surveillances, intervals for recommended Type A testing may be extended by up to 15 months.
l This option should be used only in cases where refueling schedules have been changed to accommodate other factors.
2.
Consistent with standard scheduling practices for Technical l
Specifications Required Surveillances, intervals for the recommended surveillance frequency for Type B and Type C testing may be extended by up to 25 percent of the test interval, not to exceed 15 months.
l The provisions of Surveillance Requirement 3.0.3 are applicable to the Containment Leakage Rate Testing Program.
I 1
i SAN ON0FRE--UNIT 2 5.0-20b Amendment No. 144 i
nestoq l
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UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. - =1
(**W l
SOUTHERN CALIFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CALIFORNIA THE CITY OF ANAHEIM. CALIFORNIA DOCKET NO. 50-362 SAN ONOFRE NUCLEAR GENERATING STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.135 License No. NPF-15 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southem California Edison Company, et al.
(SCE or the licensee) dated May 11,1998, as supplemented by letter dated October 9,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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.
l l
, 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-15 is hereby amended to read as follows:
(2)
Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.
135, are hereby incciprated in the license. Southern California Edison Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
i 3.
This license amendment is effective as of the date of its issuance and is to be implemented within 30 days of its issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION l
h.
A ames W. Clifford, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 6, 1998 I
l l
l 1
l
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.135 TO FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT 3.6-2 3.6-2 3.6-6 3.6-6 3.6-14 3.6-14 5.0-20a 5.0-20a 5.0-20b
Containment 3.6.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1 Perform required visual examinations and In accordance leakage rate testing except for containment with the air lock testing, in accordance with the Containment Containment Leakage Rate Testing Program.
Leakage Rate Testing Program SR 3.6.1.2 Verify containment structural integrity In accordance in accordance with the Containment Tendon with the Surveillance Program.
Containment Tendon Surveillance Program SAN ONOFRE--UNIT 3 3.6-2 Amendment No. 116,135
Containment Air Locks 3.6.2 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D.
Required Action and D.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.
AHQ D.2 Be in MODE 5.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1
NOTES-------------------
1.
An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.
2.
Results shall be evaluated against acceptance criteria applicable to SR 3.6.1.1.
Perform required air lock leakage rate In accordance testing in accordance with the Containment with the Leakage Rate Testing Program.
Containment Leakage Rate Testing Program e
(continued)
SAN ONOFRE--UNIT 3 3.6-6 Amendment No. 116,135
Containment 150lattoW "3.6.3 FREQUENCY REMENTS (continued)
. LANCE REQUI SURVEILLANCE diation
-NOTES in high ra y
3.6.3.4 Valves and blind flangesverified by use f 4
o g
- 1. areas may be means.
administrative p
ble.
7
- 2. SR 3.0.4 is not applica..................
/
Prior toentering MODE 4 j
manual valve from. MODE 5 if isolationlocated inside d to be losed during not performed Verify each containment and blind flange that is within the L
c closed, except for containment and require valves that are pen previous o
accident conditions is 92 days
/
containment isolationcontrols.
administrative under In accordance of each Section A with the Inservice Verify the isolation timed each automaticwithin limits.
Testing Program and B power operated anvalve is 3.6.3.5 containment isolation SR
/
/,
/
l evaluated against accepNOTES.
tance 3.6.3.6 ults hall beapplicable to SR 3.6.1.1..................
184 days s
i Res SR criteria.........................containment rate testing for LNQ.
Perf orm leakagewith resilient seals. Within 92 days valves opening purge after the valve (continued) 116,135 Amendment No.
3.6-14 SAN ONOFRE. UNIT 3
Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs,andManuals(continued) 5.5.2.14 Configuration Risk Management Program (CRMP)
(Continued) d.
Provisions for assessing the need for additional actions after the discovery of additional equipment out of service conditions while in the LCO Condition.
e.
Provisions for considering other applicable risk significant contributors such as Level 2 issues, and external events, qualitatively or quantitatively.
5.5.2.15 Containment Leakage Rate Testing Program 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 50, Appendix J, Option B, as modified by approved exemptions. This
)rogram shall be in accordance with the guidelines contained in legulatory Guide 1.163, " Performance-Based Containment Leak-Test Program", dated September 1995.
The calculated peak containment internal pressure related to the design basis loss-of-coolant accident, P., he calculated (pe. will is 55.1 psig P conservatively be assumed to be equal to t ak containment internal pressure for the design basis Main Steam Line Break (56.6 psig) for the purpose of containment testing in
. accordance with this Technical Specification).
The maximum allowable containment leakage rate, L,, at P., shall be 0.10% of containment air weight per day.
Leakage rate acceptance criteria are:
a.
The Containment overall leakage rate acce)tance criterion is s 1.0 L During the first unit startup "ollowing testing in accordan,.ce with this program, the leakage rate acceptance criteria are s 0.60 L, A tests;for the Type B and Type C tests and s 0.75 L, for the Type b.
Air lock testing acceptance criteria are:
1)
Overall air lock leakage rate is s 0.05 L, when tested at 2 P,.
2)
For each door, the leakage rate is s 0.01 L, when pressurized to 2 9.0 psig.
SAN ONOFRE--UNIT 3 5.0-20a Amendment No. 1165131,135
,,,-----4
- m.,. -,, - -,
w
-y v
.r
- - ---.... - =
.. -- _ -.__ - _=.
I Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals (continued) l l
5.5.2.15 Containment Leakage Rate Testing Program (Continued) l The provisions of Surveillance Requirement 3.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing l
Program.
However, test frequencies specified in this Program may be extended consistent with the guidance provided in NEI 94-01, i
" Industry Guideline For Implementing Performance-Based Option Of l
10CFR 50, Appendix J," as endorsed by Regulatory Guide 1.163.
Specifically, NEI 94-01 has these provisions for test frequencies extension:
1.
Consistent with standard scheduling practices for Technical Specifications Required Surveillances, intervals for recommended Type A testint may be extended by up to 15 months.
This option should be usec: only in cases where refueling schedules have been changed to accommodate other factors.
2.
Consistent with standard scheduling practices for Technical Specifications Required Surveillances, intervals for the recommended surveillance frequency for Type B and Type C testing may be extended by up to 25 percent of the test.
interval, not to exceed 15 months.
The provisions of Surveillance Requirement 3.0.3 are applicable to the Containment Leakage Rate Testing Program.
?
SAN ONOFRE--UNIT 3 5.0-20b Amendment No.135
-