ML13310A428
| ML13310A428 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 06/02/1982 |
| From: | Southern California Edison Co |
| To: | |
| Shared Package | |
| ML13310A429 | List: |
| References | |
| NUDOCS 8206070226 | |
| Download: ML13310A428 (10) | |
Text
BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION Application of SOUTHERN CALIFORNIA EDISON COMPANY, ET AL. for a Class 103 license to DOCKET NO. 50-361 Acquire, FPssess, and Use a Utilization Facility as Part of Unit No. 2 of the San
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Amendment Application Onofre Nuclear Generating Station
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No. 4 SOUTHERN CALIFORNIA EDISON COMPANY, ET AL. pursuant to 10 CFR 50.90, hereby submit Amendment Application No. 4.
This amendment application consists of Proposed Changes NPF-10-18 and NPF-10-19 to Technical Specifications incorporated in Facility Operating License No. NPF-10 as Appendix A. Proposed Change NPF-10-18 is a request to revise Technical Specification 3.3.2 to clarify Table 3.3-5, Items 2.a(5)(b) and 3.a(4)b. Proposed Change NPF-10-19 is a request to revise Technical Specification 3.3.2 to clarify Table 3.3-5, Items 8.a(2) and 9.a(2).
Pursuant to 10 CFR 170.22 proposed changes contained in Amendment Application No. 4 are considered to constitute a Class II Amendment. The basis for the determination is that the changes have no safety or environmental significance.
Accordingly, the fee of $2,400.00 corresponding to this determination is remitted herewith as required by 10 CFR 170.22.
8206070226 820602 PDR ADOCK 05000361 PDR
NPF-10-18 Rev. 1 DESCRIPTION OF PROPOSED CHANGE NPF-10-18 AND SAFETY ANALYSIS K
OPERATING LICENSE NPF-10 This is a request to revise Appendix "A" Technical Specification 3.3.2, Table 3.3-5 items 2.a(5)(b), 3.a(4)(D), and associated NOTE 4, ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRJMENTATION.
Existinq Specification See Attactment A Proposed Specification See Attachment B Reason for Proposed Change The response time of containment emergency cooler CCW isolation valves must be limited by the Technical Specifications in order to assure that the containment emergency cooler system will operate in accordance with the specific assumptions of the containment pressure analyses (as described in FSAR Section 6.2, Tables 6.2-25 and 6.2-26). The CCW non-critical loop isolation valves were inadvertantly listed in lieu. of the Containment emergency cooler CCW isolation valves in the Technical Specifications; in addition. the implied 10 second stroke time for the valves has been revisea to 12 seconds per FSAR Amendment 29 and the previously omitted 10 second allowance for emergency diesel operator starting and load seQuencing has been added since these are A-C motor operated valves, making a correct total response time of 23.2/23.0 seconds in lieu of 11.2/11.0 seconds for these valves.
Although a response time limit for the CCW non-critical loop isolation Rev.
valves is not required by the containment pressure analyses(as described in FSAR Section 6.2, Tables 6.2-25 and 6.2-26), the high energy line break analyses(described in FSAR Section 3.6) do require a response time limit for these valves to ensure integrity of the CCW critical loops following the rupture of non-critical loop
.piping-by certain large-break LOCA's. It is therefore prudent to retain a Technical Specification limit on CCW non-critical loop isolation valve response time; the correct stroke time limit for these valves is 20 seconds, in lieu of the 10 seconds which pertained to the containment emergency cooler CCW isolation valves.
(Since these are pneumatic valves, the 10 seconds for emergency diesel geerator starting and load sequencing do not apply.)
Safety Analysis of Proposed Change The containment pressure analyses (described in FSAR Section 6.2, Tables 6.2-25 and 6.2-26) assume a specific maximum response time for the containment emergency cooler CCW isolation valves (i.e., a 12 second valve stroke time).
Including the applicable load sequencing and emergency diesel generator -starting time for -these aec-motor operated-valves-(10 seconds)-and-SIAS instrumentation and logic response times (1.2 seconds for pressurizer pressure-low, 1.0 seconds for containment pressure-high), the required Technical Specification limit for overall response time of this safety function is 23.2 seconds (pressurizer pressure-low) and 23.0 seconds (containment pressure-high), as marked. Inclusion of these limits for valves HV-6366 through HV 6373 will assure compliance of the containment emergency cooling.function to the safety analysis response time assumptions.
The CCW non-critical loop isolation valves are required to close in order to preserve the integrity of the connected critical loop shoulc any of the non-critical loop piping inside containment be imDinoed in the course of a high energy line break (described in FSAR Section 3.6).
Including the applicable SIAS instrumentation and logic response times, the required Technical Specification limit for overall response time of this safety function is 21.2 seconds (pressurizer pressure-low) and 21.0 seconds (containment pressure-high), as marked. Inclusion of these limits for valves HV-6212, Hv-5213, HV-6218 and HV-6219 will assure compliance of the containment emergency cooling function to the safety analysis response time assuumpti ons.
Accordingly, it is concluoed that:
(1) Proposed Change NPF-10-18 does not involve an un-eviewed safety question as defined in 10 CFR 50.59, nor does it present significant hazard considerations not describec or implicit in the Final Safety Analysis; (2) there is reasonable assurance tnat tne health and safety of the public will not be endangered by the proposec change; and (3) this action will not result in a condition which significantly alters the impact of the station on the environment as described in tne NRL Final Environmental Statement.
NPF-1U-18 ATTACHMENT A
Existing Specification:
- 2.
Pressurizer Pressure-Low
- a.
SIAS (1) Safety Injection (a) High Pressure Safety Injection 31.2*
(b) Low Pressure Safety Injection 41.2*
(2) Control Room Isolation Not Applicable (3) Containment Isolation (NOTE 3) 11.2* (NOTE 2)
(4)
Containment Spray (Pumps) 25.6*
(5) Containment Emergency Cooling (a) CCO Pumps 31.2*
b CCW Valves (NOTE 4) 11.2 c
Emergency Cooling Fans 21.2*
- 3. Containment Pressure-High
- a. SIAS (1) Safety Injection (a) Hign Pressure Safety Injection 41.U*
(b) Low Pressure Safety Injection 41.0*
(2)
Control Room Isolation Not Applicable (3) Containment Spray (Pumps) 25.4*
(4) Containment Emergency Cooling Sa)
CCW Pumps 31.0*
b) CCW Valves 11.0 (NOTE 4)
(c) Emergency Cooling Fans 21.0*
NOTES:
- 1. Response times include movement of valves ano attainment of pump or blower discrarge pressure as applicable.
Emergency diesel.generator starting delay (10 sec.) and sequence loading delays for SIAS are included.
- 2. --
Response time includes emergency diesel generator starting delay (applicable to AC motor operated valves other than containment purge valves), instrumentation and logic response only. Refer to Table 3.6-1 for containment isolation valve closure times.
- 3. All CIAS-Actuated valves except MSIVs and MFIVs.
- 4.
CCW non-critical loop isolation valves 2HV-6212, 2HV-6213, 2HV-6218 and 2HV-2619.
- 5. Response time includes instrumentation, logic, and isolation damper closure times only.
NPF-10-18 ATTACHMENT B
Proposed Specification:
- 2.
Pressurizer Pressure-Low
- a.
SIAS (1) Safety Injection (a) High Pressure Safety Injection 41.2*
(b) Low Pressure Safety Injection 12 (2) Control Room Isolation Not Applicable (3) Containment Isolation (NOTE 3) 11.2* (NOTE 2)
(4) Containment Spray (Pumps) 25.6*
(5) Containment Emergency Cooling (a) CCW Pumps 31.2*
(b) CCW Valves (NOTE 4a) 21.2 (c)
CCW valves (NOTE 4b)
(d) Emergency Cooling Fans 21.2*
- 3.
Containment Pressure-High
- a. SIAS (1) Safety Injection (a) High Pressure Safety Injection 41.0*
(b) Low Pressure Safety Injection 41.0*
(2) Control Room Isolation Not Applicable (3)
Containment Spray.(Pumps) 25.4*
(4)
Containment Emergency Cooling (a)
CCW Pumps 31.0*
(b)
CCW Valves (NOTE 4a) 21.0 (c) CCW Valves (NOTE 4b) 23.0*
(d) Emergency. Cooling Fans 21.0*
NOTES:
- 1. Response times include movement of valves and attainment of pump or blower discharge pressure as applicable.
Emergency diesel generator starting delay (10 sec.) and sequence loading delays for SIAS are included.
- 2. Response time includes emergency diesel generator starting delay (applicable to AC motor operated valves other than containment purge valves), instrumentation and logic response only.
Refer to Table 3.6-1 for containment isolation valve closure times.
Retyped Page
-2
- 3. All CIAS-Actuated valves except MSIVs and MkIVs.
4a. CCW non-critical loop isolation valves 2HV-6212, 2HV-6213, 2HV-6218 and 2HV-2619 close.
4b. Containment emergency cooler CCW isolation valves 2HV-6366, 2HV-6367, 2HV-6368, 2HV6369, 2HV6370, 2HV6371, 2HV6372, 2HV6373 open.
- 5. Response time includes instrumentation, logic, and isolation damper closure times only.
NPF-10-19 Rev. 0 DESCRIPTION OF PROPOSED CHANGE NPF-10-19 AND SAFETY ANALYSIS This is a request to revise Appendix "A" Technical Specification 3.3.2, Table 3.3-5.
ENGINEERED SAFETY FEATURES RESPONSE TIMES EXISTING SPECIFICATION:
See Attachment "A" PROPOSED SPECIFICATION:
Page Add to the end of Surveillance Requirement 4.3.2.3:
"The provisions 3/4 3-13 of specification 4.0.4 are not applicable for entry into Mode 3 for items 8.a(2) and 9.a(2) of Table 3.3-5."
Page Add "(Note 6)" after items 8.a(2) and 9.a(2) of Table 3.3-5.
3/4 3-29 Page Add Note 6 as follows:
3/4 3-30 "6. The provisions of specification 4.0.4 are not applicable for entry into Mode 3."
SAFETY ANALYSIS:
The turbine driven auxiliary feedwater pump is not tested for operability,,as specified in Specification 4.7.1.2.1.a.1, until after entry into Mode 3, when adequate steam pressure exists in steam generators to permit the pump to function as designed. This change is consistent with such requirements since proper determination of ESF response times for the turbine driven auxiliary feedwater pump is dependent upon having adequate steam pressure available.
Accordingly, it is concluded that:
(1) Proposed Change NPF-10-19 does not involve an unreviewed safety question as defined in 10 CFR 50.59, nor does it present significant hazard considerations not described or implicit in the Final Safety Analysis; (2) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed change; and (3) this action will not result in a condition which significantly alters the impact of the station on the-environment as described in the NRC Final Environmental Statement.
HRP:4307
NPF-10-19 ATTACHMENT A