ML20155B863

Application for Amends to Licenses NPF-10 & NPF-15, Respectively.Proposed Change Number 485 Adds SR to TS 3.3.9, CR Isolation Signal

ML20155B863
Person / Time
Site:	San Onofre
Issue date:	10/20/1998
From:	Nunn D SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20155B858	List: ML20155B852 ML20155B863 ML20155B874
References
NUDOCS 9810300318
Download: ML20155B863 (9)

Text

. ._ ._ . _ _ . _ _ _ . __ -. _ _ _ . _ . _ . . _ . . _ . _ - . . _ _ _ _ _ _ _ _ _ _ _ _ . _ _

l .o l

UNITED STATES OF AMERICA HUCLEAR REGULATORY COMISSION I-Application of SOUTHERN CALIFORNIA )

EDIS0N COMPANY, H AL. for a Class 103 ) Docket No. 50-361

License to Acquire, Possess, and Use )

a Utilization Facility as Part of ) Amendment Application l Unit No. 2 of the San Onofre Nuclear ) No. 173 Generating Station )

l SOUTHERN CALIFORNIA EDIS0N COMPANY, H AL. pursuant to 10 CFR 50.90, hereby submit Amendment Application No. 173. This Amendment Application consists of Proposed Change Number 485 (PCN 485) to Facility Operating License No. NPF-10.

l PCN 485 adds a Surveillance Requirement to Technical Specification 3.3.9,

" Control Room Isolation Signal (CRIS)." The new Surveillance Requirement provides for response time testing of CRIS.

)

9810300318 981020 ^

PDR ADOCK 05000361 P PDR-

)

Subscribed on this dey FOR of "h br , 12,s.

Respectfully submitted, SOUTHERN CALIF 0 IA EDISO COMPANY B W s

= --

Dwight E. N in j Vice President j i

. {

State of California  !

O Countyof[SanDfdof/

On /O >o ,9efore me,l /lCtrkLn6 . y/ 38Miy l appeared bMMhd/ /UbllWhrsonally known to me to be the person whose name is subscribed to the within instrument and acknowledged to me that he j executed the same in his authorized capacity, and that by his signature on the instrument the person, or the entity upon behalf of which the person acted,  :

executed the instrument.  !

WITNESS my hand and official seal.

l

.m ...... .. ,

MARIANE sANCHEZ Commission #1196482

- j-9 NotaryPutic-Coli l 7

J son Dieoo County 1 MyComm,EmirdOct14ZD2 >

Signaturf -

(L' ' _

I

1 1

e9 i

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION 1

Application of SOUTHERN CALIFORNIA )

EDIS0N COMPANY, El AL. for a Class 103 )' Docket No. 50-362 j License to Acquire, Possess, and Use )

a Utilization Facility as Part of ) Amendment Application ,

Unit No. 3 of the San Onofre Nuclear ) No. 159 l Generating Station )

SOUTHERN CALIFORNIA EDISON COMPANY, EI 6L. pursuant to 10 CFR 50.90, hereby submit Amendment Application No. 159. This Amendment Application consists of Proposed Change Number 485 (PCN 485) to Facility Operating License No. NPF-15.

PCN 485 adds a Surveillance Requirement to Technical Specification 3.3.9, l

" Control Room Isolation Signal (CRIS)." The new Surveillance Requirement j provides for response time testing of CRIS.

i I

r 1-4 4

l i

l l

1 l

Subscribed on this day of b 09.I , 1998.

Respectfully submitted, SOUTHERN CALIFORNIA EDIS0N COMPANY

- t Byk( '

.A v DwightE.Nh nn Vice President State of California County f San [ieg n -

Onf BON 3efore m / b lUA O (. / bi h4 h b ly appearedh}O /N bllM,hersonally known to me to be the person whose name is subscribed to the within instrument and acknowledged to me that he executed the same in his authorized capacity, and that by his signature on the instrument the person, or the entity upon behalf of which the person acted, executed the instrument.

WITNESS my hand and official seal, n -----.. ----

MARtANE sANCHE1 Commission #1196482 NotcryPvtAc Cofifamic f 0 ,

[]9MC 4

sm Diego County r onmEghsOct14.2002 >

Signature l

I 1 .'

l e' l l

l l DESCRIPTION AND SAFETY ANALYSIS l . .

OF PROPOSED CHANGE NUMBER 485 This is a request to revise Section 3.3.9, " Control Room Isolation Signal (CRIS)"

of the Technical Specifications for San Onofre Nuclear Generating Station Units 2

& 3.

Existina Technical Specification Unit 2: See Attachment "A" p Unit 3: See Attachment "B" Etooosed Technical Specification l Unit 2: See Attachment "C" red line and strikeout Unit 3: See Attachment "D" red line and strikeout Prooosed Technical Specification Unit 2: See Attachment "E" ,

Unit 3: See Attachment "F" Proposed Bases (for information)

Unit 2: See Attachment G Unit 3: See Attachment H Dascriotion of Chugn Summary Presently Technical Specification Section 3.3.9, " Control Room Isolation Signal (CRIS)." does not require a response time surveillance test for the Control Room AirborneRadiationMonitors,2/3RE7824-1and2/3RE7825-2.

A surveillance that tests the time it takes to isolate the control room af ter an au.'omatic high radiation generated CRIS and a Safety Injection Actuation Signal (SIAS) generated CRIS is needed to ensure compliance with the design basis.

This proposed change will add a Surveillance Requirement (SR 3.3.9.6) to verify CRIS response time is within limits. The surveillance will ensure that the train actuation response time is less than or equal to the maximum time assumed in the analyses. A time limit to isolate the control room is needed to ensure compliance with 10 CFR Part 50 Appendix A General Design Criterion (GDC) 19.

l

.5

.o l

Discussion l . .

l l 10 CFR 50 Appendix A, GDC 19 requires that: " Adequate radiation protection shall be provided to permit access to and occupancy of the control room under accident conditions without personael receiving radiation exposures in excess of 5 rem whole body, or its equivalent to any part of the body, for the duration of the accident."

Section C.2.i of NRC Regalatory Guide 1.52 states: "Unless the applicable engineered-safety-feature atmosphere cleanup system operates continuously during all times that a Design Basis Accident (DBA) can be postulated to occur, the system should be automatically activated upon the occurrence of a DBA by (1) a

redundant engineered-safety-feature signal or (2) a signal from redundant Seismic j Category 1 radiation monitors."

l Safety related, redundant, airborne radiation monitors 2/3RT7824-1 and 2/3RT7825-l 2 continuously monitor the outside air supply to the control room when the normal HVAC is in service. The monitors are designed in accordance with 10 CFR 50, Appendix A, Section III which specifies the general design criteria for instrumentation that performs Engineered Safety Features Actuation System i j . functions.

l If the radioactivity concentration reaches the monitors' trip setpoint value, the i

monitors will initiate a CRIS which will isolate the normal air conditioning unit i

and actuate the emergency air conditioning units. In addition, CRIS will be initiated on an SIAS. Actuation of one CRIS channel will close the normal air conditioning unit's isolation dampers, trip the normal air conditioning unit's supply fan, and start the associated train of the redundant emergency air '

conditioning units to provide filtered outside air to the control room.

Calculations have been issued which model control room isolation following i specified DBA's. In order for control room dose requirements to be met, the

[ control room isolation dampers must close within a specified time period.

L Thefollowingcalculationrevisionsandchangenoticeshavebeenissuedtodetail

! the control room isolation model for the DBA s.

l N-4072-001 Rev.4 (CCN-3) FHA Inside FHB-CR & Offsite Doses i

N-4072-003 Rev.2 (CCN-2) FHA Inside Containment-CR & Offsite Doses N-4075-004 Rev.2 Doses for Revised SGTR Event N-4077-001 Rev.7 (CCN-1) Letdown Line Break Offsite Ooses N-4060-004 Rev.8 (CCN-3) LOCA-Containment Leakage-CR Dose J-SPA-179 Rev.0 Control Room / Fuel Handling Building Monitor Setpoints The proposed change will add a surveillance test to the Surveillance Requirements of Technical Specification Section 3.3.9. The addition will be " Verify that l

4

response time of required CRIS channel is within limits." The surveillance frequency will be 18 months, which corresponds to the frequency of the CRIS Channel Functional and Calibration tests. The frequency is based on plant operating experience with regard to channel operability, which demonstrates that failure of one or more channels of a given function in any 18 month interval is a rare event. The frequency is also based upon plant operating experience that shows that random failures of instrumentation components causing serious response time degradation, but not channel failure, are infrequent occurrences.

There are no significant safety hazards considerations since this is an addition I to the Technical Specifications with the purpose of verifying compliance with 10 CFR Part 50 Appendix A GDC 19.

Revised Bases corresponding to the addition of this Surveillance Requirement are provided for information in Attachments G and H. Licensee Controlled Specification 3.3.100, "RPS/ESFA Response Times," will be updated following NRC i approval of this proposed change to include response times for control room '

isolation for SIAS and for Control Room airborne radiation. i l

No Sianificant Hazards Considerations  !

l The Commission has provided standards for determining whether a significant j hazards consideration exists as stated in 10 CFR 50.92. A proposed amendment to I an operating license for facility involves no significant hazards consideration '

if operation of the facility in accordance with a proposed amendment would not:

(1) involve a significant increase in the probability or consequences of an accidentpreviouslyevaluated;or(2)createthepossibilityofanewor different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. A discussion of these standards as they relate to this amendment request follows:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No The proposed change will maintain the Control Room Isolation Signal (CRIS) o)erability and surveillance requirements in the Technical Specification.

T1e proposed change only adds response time testing. The probability of an accident and the consequences of an accident are unaffected by this proposed change since the Safety Analysis remains unaffected. Therefore, operation of the facility in accordance with this change will not involve an increase in the probability or consequences of an accident previously evaluated.

2. Create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No Addition of response time testing will not alter the design and operational interface between the CRIS instrumentation and existing plant ecuipment.

The monitors will continue to operate and perform their intendec safety function to isolate the control room tollowing a design basis accident as before. Therefore, operation of the facility in accordance with this proposed change will not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Involve a significant reduction in a margin of safety?

Response: No This proposed change will not affect the margin of safety since this is an

! addition to the Technical Specifications with the purpose of verifying compliance with 10 CFR Part 50 Appendix A General Design Criterion 19.

Addition of response time testing will verify this specific margin of safety.

)

Based on-the responses to these three criterion, Southern California Edison (SCE) has concluded that the proposed amendment involves no significant hazards consideration.

t

! Environmental Consideration:

SCE has determined that the proposed amendment involves no changes in the amount

! or type of effluent that may be released offsite, and results in no increase in individual or cumulative occupational radiation exposure. As described above, the proposed Technical Specification amendment involves no significant hazards consideration and, as such, meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) l l

j i

PCN-485 i

l l

ATTACHMENT "A" EXISTING SPECIFICITIONS UNIT 2

. . .. .