ML20113C254

Application for Amends 159 & 143 to Licenses NPF-10 & NPF-15 Revising TS 3.3.11, Pami, & TS 5.5.2.13, Diesel Fuel Oil Testing Program

ML20113C254
Person / Time
Site:	San Onofre
Issue date:	06/25/1996
From:	Nunn D SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20113C242	List: ML20113C240 ML20113C254 ML20113C256
References
NUDOCS 9607010077
Download: ML20113C254 (11)

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I UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Application of SOUTHERN CALIFORNIA i EDIS0N COMPANY, H g . for a Class 103 Docket No. 50-361 License to Acquire, Possess, and Use a Utilization Facility as Part of Amendment Application Unit No. 2 of the San Onofre Nuclear No. 159.

Generating Station ,

I l l I l SOUTHERN CALIFORNIA EDISON COMPANY, H g pursua.nt to 10 CFR 50.90, hereby l \

submit Amendment Application No. 159.

This amendment application consists of Proposed Technical Specification Change No. NPF-10-466, Supplement 1 to Facility Operating License NPF-10. Proposed Technical Specification Change No. NPF-10-466, Supplement 1, is a request to revise Technical Specification TS 3.3.11, " Post Accident Monitoring Instrumentation (PAMI)," and TS 5.5.2.13 " Diesel Fuel Oil Testing Program,"

approved by NRC Amendment No. 127.

l The proposed change would correct the number of instruments required to measure Reactor Coolant Inlet Temperature (Tcoid), and Reactor Coolant Outlet Temperature (Twot), from two per loop to two (one per steam generator), and revise criteria for diesel fuel oil testing.

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9607010077 960625 PDR ADOCK 05000361 P PM

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Application of SOUTHERN CALIFORNIA )

EDISON COMPANY, El AL. for a Class 103 ) Docket No. 50-362 License to Acquire, Possess, and Use a Utilization Facility as Part of Amendment Application Unit No. 3 of the San Onofre Nuclear No. 143.

Generating Station )

SOUTHERN CALIFORNIA EDISON COMPANY, ET AL. pursuant to 10 CFR 50.90, hereby submit Amendment Application No. 143.

This amendment application consists of Proposed Technical Specification Change

! No. NPF-15-466, Supplement 1 to Facility Operating License NPF-15. Proposed Technical Specification Change No. NPF-15-466, Supplement 1, is a request to i revise Technical Specification TS 3.3.11, " Post Accident Monitoring Instrumentation (PAMI)," and TS 5.5.2.13, " Diesel Fuel Oil Testing Program,"

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approved by NRC Amendment No. 127. l The proposed change would correct the number of instruments required to measure Reactor Coolant Inlet Temperature (Te ge), and Reactor Coolant Outlet >

Temperature (Tut), from two per loop to two (one per steam generator), and revise criteria for diesel fuel oil testing.

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e Subscribed on thi day of WMs , 1996.

V l Respectfully submitted, SOUTHERN CALIFORNIA EDIS0N COMPANY B: ~

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DwightE.Nu%

Vice President State of California County f San Diego On b cl'$ f $le before me klO (14 I(bkpersonally appeared [k0iGhh b. Mtinn , personally known to me fn pmvud iu me-on.the4 asis-of-satisfactnry_exidehbe_.the person'tQ whose nameh{

is/are subscribed to the within instrument and acknowledged to me that l he/she/they executed the same in his/her/their authorized capacityheQ, and i

that by his-/her/4 hair signatureh) on the instrument the person 1Q, or the entity upon behalf of which the personN acted, executed the instrument.

l WITNESS my hand and official seal. . . , , , , , , , , , , , , , ,

MARIANE SANCHEZ CcNM. # 1033763 f

l Notory PubRe - Cof,fornia h Signature d

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Com we CT 4.1993 l

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l Subscribed on this 5+1 day of % M i b , 1996. l I 1 1

Respectfully submitted, I i

SOUTHERN CALIFORNIA EDISON COMPANY

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l By: m .

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Dwight'E. Nunn Vice President l

State of California County f San D ego .

On (D h before me, l[IIAdd ~ I (Ipersonally appeared YldtGh7 G . OtArm , pers'ena'11y known to me -(or- preved tc rs' l ort.ththaEis-ol-sethfactory-evidence) to be the personTA whose namebL i 1s/+ee subscribed to the within instrument and acknowledged to me that he/&/+%y executed the same in his/hp/eetr authorized capacity (feQ, and l

that by his/her/the+r signaturetQ on the instrument the person'M, or the entity upon behalf of which the personKacted, executed the instrument.

WITNESS my hand and official seal. '^^^^-u . _m ,

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MAMANE SANCHEZ g ', .- COMM. # 1333763 f.

/ A Notcry Public - Cc<fornlo I E ORANGE CocNry Signatur ii t

b) / f f [-/ , -

1_ My Corrm E::st:06 0CT 14, W;e

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l DESCRIPTION AND SAFETY ANALYSIS )

i 0F PROPOSED CHANGE NPF-10/15-466, Supplement 1 l

l This is a request to revise 3.3.11. " Post ,4ccident Monitoring Instrumentation i

(PAMI)," and 5.5.2.13, " Diesel fuel Oil Testing Program," for SONGS Units 2 ar.d 3.

Technical Specifications 3.3.11, and 5.5.2.13 were approved by NRC Amendment Nos. 127 and 116.

Existina SONGS Specifications:

Unit 2: See Attachment "A" Unit 3: See Attachment "B" ProDosed SONGS Specifications: l Unit 2: See Attachment "C" l Unit 3: See Attachment "D" Description of Chanaes l

Summary i Proposed Technical Specification Change Number NPF-10/15-466 (PCN-466),

Supplement 1 addresses modifications to the Technical Specifications for the San Onofre Nuclear Generating Station (SONGS) Units 2 and 3 approved by NRC ,

Amendment Nos. 127 and 116. NRC Amendment Nos. 127 and 116 approved a license I amendment request that adopted the recommendations of NUREG-1432, " Standard Technical Specifications Combustion Engineering Plants," requested through Proposed Technical Specification Change Number NPF-10/15-299 (PCN-299).

PCN-466, Supplement I would revise Technical Specification (TS) TS 3.3.11, i

" Post Accident Monitoring Instrumentation (PAMI)," and TS 5.5.2.13, " Diesel Fuel Oil Testing Program," for SONGS Units 2 and 3.

The proposed change is required to restore certain provisions of the current Technical Specifications that were not properly incorporated in PCN-299.

Specifically, the number of instruments required to measure Reactor Coolant Ir.let Temperature (Teoig), and Reactor Coolant Outlet Temperature (Tm),will be revised from two per loop to two (with one cold leg RDT and one hot leg RTD per steam generator), and criteria for diesel fuel oil testing requirements would be revised also.

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Discussion >

Through Proposed Technical Specification Change No. NPF-10/15-299 (PCN-299), j changes to the SONGS Units 2 and 3 Technical Specifications were proposed that  ;

would adopt the recommendations of NUREG-1432, " Standard Technical  !

Specifications Combustion Engineering Plants." These changes included  !

incorporating the revised format of the NUREG, including allowances granted by NUREG-1432, plant specific differences, and to a limited degree, changes to reflect plant specific enhancements. Mainly, the SONGS Units 2 and 3 i Technical Specifications were directly transcribed in PCN-299. NRC Amendment l Nos. 127 and 116, dated February 9, 1996, approved the changes proposed '

through PCN-299.

Proposed Technical Specification Change Number NPF-10/15-466 (PCN-466),

Supplement 1 addresses modifications to the SONGS Units 2 and 3 Technical Specifications approved by NRC Amendment Nos.127 and 116. During preparation of the procedure changes necessary to implement NRC Amendment Nos.127 and 116, certain changes required to implement these amendments were l identified. The proposed changes discussed herein would restore particular

! provisions of the SONGS Units 2 and 3 Technical Specifications that were not properly incorporated in PCN-299.

Changes are proposed that would revise: a) TS 3.3.11, " Post Accident Monitoring Instrumentation (PAMI)," and b) TS 5.5.2.13, " Diesel Fuel Oil Testing Program." <

l The following discussion describes the proposed changes.

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a) The proposed change would revise TS 3.3.11, " Post Accident Monitoring Instrumentation (PAMI)." TS 3.3.11 is required to ensure that necessary plant parameters are displayed that provide information required by the control room operators during postulated accident conditions. TS 3.3.11 requires operability of. Regulatory Guide 1.97 Type A variables and Category I, non-Type A variables.

, The NUREG-1432 technical specifications differ from the current SONGS l Units 2 and 3 Technical Specifications in that tne NUREG identifies two channels of Reactor Coolant Inlet Temperature (T io) 4 channels of Reactor Coolant Outlet Temperature g (T loop.

per ,1) per loop, and two Under the current Technical Specifications for SONGS Units 2 and 3, l TS 3/4.3.3.6, " Accident Monitoring Instrumentation," requires j operability of two channels of Reactor Coolant Inlet Temperature (Teoie) and two channels of Reactor Coolant Outlet Temperature (T i Therefore,therewasanunintentionalincreaseinthenumbot). er of instruments required. The currently installed instrumentation satisfies the current Technical Specification, but cannot satisfy the j specification inadvertently directly transcribed from NUREG-1432. j t

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The SONGS requirements for PAMI are based on analyses performed to support Regulatory Guide 1.97, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Environs Conditions During and Following an Accident," Revision 2, 1980. SONGS Units 2 and 3 satisfies the intent of this regulatory guide with certain exceptions approved by the NRC in the May 26, 1987 letter, " Safety Evaluation for Conformance to Regulatory Guide 1.97." T and T m are identified as plant specific parameters considere{[ikype A variables. SCE identified that the instrumentation to measure these parameters deviates from the regulatory guide in that the measurement range is 50*F to 710*F rather than the specified range of 50*F to 750*F. By letter dated May 26, 1987, this was found acceptable by the NRC in their Safety Evaluation for Conformance to Regulatory Guide 1.97.

The current Technical Specifications require two RCS cold leg indications. During post accident operation with any forced reactor coolant system flow, forward or reverse RCS flow will assure that fluid at RCS cold leg temperature will be circulated through all of the cold legs. Therefore, even assuming only one cold leg temperature channel is available, cold leg temperature can be determined by the operable cold leg channel.

Under natural circulation conditions, S/Gs may be cooled at different rates and cold leg temperatures in Loops 1 and 2 may be different.

Events which result in isolating a S/G may amplify this difference. As long the cold leg temperature channel is operable in the loop with the operable S/G, an accurate determination of cold leg temperature can still be made. In the unlikely event that the cold leg temperature channel associated with the operable S/G is not available, the cold leg temperature can be derived by measuring the S/G pressure and converting to temperature using the steaa tables. Therefore, the current Technical Specification requirement for two cold leg RCS temperature channels is adequate. The proposed change will require two channels, with one cold leg RDT and one hot leg RTD per steam generator.

Similarly, if the hot leg temperature channel to the operable S/G is not available, the core exit thermocouples could be used as alternate hot leg temperature indication. Therefore, the current Technical Specification requirement for two hot leg RCS temperature channels is adequate. The proposed change will require two channels, with one cold leg RDT and one hot leg RTD per steam generator. The Bases for 3.3.11 will also be revised accordingly.

b) The proposed change would revise TS 5.5.2.13, " Diesel Fuel Oil Testing Program." TS 5.5.2.13 is the diesel fuel oil testing program required by SR 3.8.3.3 of TS 3.8.3, " Diesel Fuel Oil, Lube Oil, and' Starting Ai r. " Section 5.5.2.13.a of the program includes various sampling and

testing requirements, to be performed at least once every 92 days, and from new fuel oil prior to addition to the storage tanks. One of the l

tests verifies the kinematic viscosity. The limit specified in 5.5.2.13.a. is " greater than or equal to 4.1." The Bases for SR 3.8.3, however, specifies a limit of " greater than or equal to 1.9, but less than or equal to 4.1." The proposed change would revise the viscosity limit specified in the Administrative Controls to be consistent with the Bases to SR 3.8.3.3. The range of 1.9 to 4.1 is the acceptable viscosity range specified in ASTM-D975-81. Also, a typographical error in paragraph b is corrected. The ASTM standard for sampling fuel oil is restored to ASTM-04057-81. . The existing TS 3/4.8.1 in the SR 4.8.1.1.2.c.2 requires to obtain a sample of fuel oil in accordance with ASTM-04057-81 and to verify that particulate contamination is less than 10 mg/ liter when checked in accordance with ASTM-D2276-83, Method A.

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! Safety Analysis l' The proposed change described above shall be deemed to involve a significant hazards consideration if there is a positive finding in any one of the following areas:

1. Will operation of the facility in accordance with this proposed change involve a significant increase in the probability or i consequences of any accident previously evaluated?

, Response: No i

Proposed Technical Specification Change Number NPF-10/15-466 (PCN-466), Supplement 1 addresses modifications to the Technical Specifications for San Onofre Nuclear Generating Station (SONGS)

Units 2 and 3 approved by NRC Amendment Nos. 127 and 116. NRC Amendment Nos. 127 and 116' approved changes to adopt the recommendations of NUREG-1432, " Standard Technical Specifications Combustion Engineering Plants," requested through~ Proposed ,

Technical Specification Change Number NPF-10/15-299 (PCN-299). .

The proposed changes were identified during drafting of the procedure changes required to implement NRC Amendment Nos.127 and 116.

l PCN-466 Supplement 1 is required to restore certain provisions of

! the current Technical Specifications that were not properly

! incorporated in Amendment Nos. 127 and 116. Changes are proposed that would revise Technical Specification (TS) TS 3.3.11, " Post Accident Monitoring Instrumentation (PAMI)," and TS 5.5.2.13,

" Diesel Fuel Oil Testing Program."

Specifically, the proposed change corrects the number of instruments required to measure Tcou and Tm from two per loop to two (with one cold _ leg RDT and one hot leg RTO per steam 4 generator) in TS 3.3.11. Also, the proposed change revises diesel fuel oil testing requirements specified in TS 5.5.2.13. In

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s particular, the viscosity limit specified in the Administrative Controls is revised to the correct range per ASTM-D975-81, which is consistent with the Bases to SR 3.8.3.3. Also, a typographical )

error in paragraph b is corrected. The ASTM standard for sampling fuel oil is restored to ASTM-D4057-81.

'These provisions are contained in the current. Technical Specifications, TS 3/4.3.3.6, " Accident Monitoring Instrumentation," and in SR 4.8.1.1.2.c of TS 3/4.8.1.1, "A.C.

Sources."

0)erntion of the facility would remain unchanged as a result of l t1e proposed changes. Therefore, the proposed change will not  !

involve a significant increase in the probability or consequences of any accident previously evaluated.  ;

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2. Will operation of the facility in accordance with this proposed I change create the possibility of a new or different kind of' accident from any previously evaluated?

Response: No I c

The proposed change will. restore provisions of the current Technical Specifications for SONGS Units 2 and 3. The proposed change would correct the number of instruments required to be operable to measure Tc ig and Tuot from two per loop to two (with one cold leg RDT and one hot leg RTD per steam generator), and revise diesel fuel cil testing requirements.

Operation of the facility would remain unchanged as a result of j the proposed change. Therefore, the proposed change will not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Will operation of the facility in accordance with this proposed change involveLa significant reduction in a margin of safety?

Response: No' The proposed change will restore provisions of the current Technical Specifications.for. SONGS Units 2 and 3 and make certain 1 changes for clarity. Operation of the facility would remain unchanged as a result of the proposed change. Therefore, the proposed change will not involve a significant reduction in a margin of safety.

Safety and Sianificant Hazards Determination Based on the above Safety Analysis, it is concluded that: (1) the proposed change does not constitute a significant hazards consideration as defined by 10 CFR 50.92 and (2) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed change. Moreover, because this action does not involve a significant hazards consideration, it will also not result in a condition which significantly alters the impact of the station on the environment as described in the NRC Final Environmental l Statement.

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i NPF-10/15-466 1

ATTACHMENT "A" (Existing Specifications)

Unit 2 (

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