Text

Application for Technical Specification Improvement to Adopt TSTF-487, Revision 1, Relocate Departure from Nucleate Boiling Parameters to the Core Operating Limits Report, Using the Consolidated Line Item Improvement Process.
	ML081830515
Person / Time
Site:	San Onofre
Issue date:	06/27/2008
From:	Reilly J; Southern California Edison Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	PCN-584, TSTF-487, Rev 1
	Download: ML081830515 (31)
	v • d • e

SOUTHERN CALIFORNIA

__EDISON James T. Reilly

_O Vice President An EDISON INTERNATIONAL Company

/

June 27, 2008 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Subject:

San Onofre Nuclear Generating Station, Units 2 and 3 Docket Nos. 50-361 and 50-362 Amendment Application Numbers 251 and 237.

Application for Technical Specification Improvement to Adopt TSTF-487, Revision 1, "Relocate Departure from Nucleate Boiling (DNB)

Parameters to the Core Operating Limits Report (COLR),"

Using the Consolidated Line Item Improvement Process (CLIIP)

Proposed Change Number (PCN)-584

Dear Sir or Madam:

In accordance with the provisions of 10 CFR 50.90, Southern California Edison (SCE) is submitting a request for an amendment to the technical specifications (TS) for San Onofre Nuclear Generating Station (SONGS) Units 2 and 3.

The proposed changes would allow SONGS Units 2 and 3 to replace the DNB numeric limits in TS with references to the core operating limits report (COLR).

The changes are consistent with NRC-approved Industry Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-487 Revision 1.

The availability of this TS improvement was announced in the Federal Register on June 5, 2007, 72 FR 31108 as part of the consolidated line item improvement process (CLIIP).

Enclosure 1 provides a description and assessment of the proposed changes, as well as confirmation of applicability. Enclosure 2 provides the existing TS pages marked-up to show the proposed changes. Enclosure 3 provides final TS pages. Enclosure 4 provides the proposed changes to the TS Bases pages.

SCE requests approval of the proposed license amendments by December 31, 2008, with the amendments being implemented within 60 days.

In accordance with 10 CFR 50.91, a copy of this application, with enclosures, is being provided to the designated California Official.

P.O. Box 128 San Clemente, CA 92674-0128 Aoot 949-368-3780 Fax 949-368-3770

Document Control Desk June 27, 2008 I declare under penalty of perjury that the foregoing is true and correct.

Executed on 4-ýLe 1--2,7, 2008.

Date' If you should have any questions regarding this submittal, please contact Linda Conklin at (949) 368-9443.

Sincerely,

Enclosures:

I. Description and Assessment of Proposed Changes

2. Proposed Technical Specification Changes

3. Final Technical Specification Pages

4. Proposed Technical Specification Bases Changes cc: N. Kalyanam, NRC Project Manager, San Onofre Units 2 and 3 E. E. Collins, Regional Administrator, NRC Region IV G. G. Warnick, NRC Senior Resident Inspector, San Onofre Units 2 and 3 S. Y. Hsu, California Department of Public Health, Radiologic Health Branch R. B. Elliott, NRC ITSB Branch Chief

ENCLOSURE 1 Description and Assessment of Proposed Changes

DESCRIPTION AND ASSESSMENT OF PROPOSED CHANGES NPF-10/15-584 PROPOSED TECHNICAL SPECIFICATION 3.4.1 AND 5.7.1 CHANGES TO RELOCATE THE DEPARTURE FROM NUCLEATE BOILING (DNB) PARAMETERS TO THE CORE OPERATING LIMITS REPORT (COLR)

San Onofre Nuclear Generating Station (SONGS) Units 2 and 3

1.0 DESCRIPTION

This letter is a request to amend Operating Licenses NPF-10 and NPF-15 for San Onofre Nuclear Generating Station (SONGS) Units 2 and 3. The proposed changes would revise Technical Specification (TS) 3.4.1, "Reactor Coolant System (RCS)

Departure from Nucleate Boiling (DNB) (Pressure, Temperature, and Flow) Limits," the bases for TS 3.4.1, and 5.7.1.5 "Core Operating Limits report (COLR)," to allow SONGS Units 2 and 3 to replace the DNB numeric limits with references to the COLR.

Technical Specification Task Force (TSTF) change traveler TSTF-487, Revision 1 "Relocate DNB Parameters to the COLR" was announced for availability in the Federal Register on June 5, 2007 as part of the consolidated line item improvement process (CLIIP).

2.0 PROPOSED CHANGE

S Consistent with NRC-approved TSTF-487 Revision 1, the following changes are proposed.

Revise the limiting conditions for operation and surveillance requirements in TS 3.4.1 to replace the DNB numeric limits for reactor coolant pressure, temperature, and flow with references to limits for those parameters calculated in the COLR.

Revise the bases associated with TS 3.4.1 to reflect that the DNB numeric limits are contained in the COLR.

Revise TS 5.7.1.5 to add the methodology requirements for calculating the DNB numeric limits in the COLR.

3.0 BACKGROUND

The background for this application is as stated in the model SE in NRC's Notice of Availability published on June 5, 2007 (72 FR 31108), and TSTF-487, Revision 1.

4.0 TECHNICAL ANALYSIS

SCE has reviewed Generic Letter 88-16, and the model SE published on March 15, 2007 (72 FR 12223) as part of the CLIIP Notice for Comment. SCE has applied the methodology in Generic Letter 88-16 to develop the proposed TS changes. SCE has also concluded that the justifications presented in TSTF-487, Revision 1 and the model SE prepared by the NRC staff are applicable to SONGS Units 2 and 3, and justify this amendment for the incorporation of the changes to the SONGS Units 2 and 3 TS.

5.0 REGULTORY ANALYSIS A description of the proposed change and its relationship to applicable regulatory requirements and guidance was provided in the NRC Notice of Availability published on June 5, 2007 (72 FR 31108), the NRC Notice for Comment published on March 15, 2007 (72 FR 12223), and TSTF-487, Revision 1.

6.0 NO SIGNIFICANT HAZARDS CONSIDERATION SCE has reviewed the proposed no significant hazards consideration determination published in the Federal Register on June 5, 2007 (72 FR 31108) as part of the CLIIP. SCE has concluded that the proposed determination presented in the notice is applicable to SONGS Units 2 and 3 and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91 (a).

7.0 ENVIRONMENTAL EVALUATION SCE has reviewed the environmental consideration included in the model SE published in the Federal Register on June 5, 2007 (72 FR 31108) as part of the CLIIP. SCE has concluded that the staff's findings presented therein are applicable to SONGS Units 2 and 3 and the determination is hereby incorporated by reference for this application.

ENCLOSURE 2 2 a. Proposed Unit 2 Technical Specification Changes (Mark-Up)

RCS DNB (Pressure, Temperature, and Flow) Limits 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS DNB (Pressure, Temperature, and Flow) Limits LCO 3.4.1 RCS parameters for pressurizer pressure, cold leg temperature, and RCSS*.*I_*flow rate shall be within the limits specified in the COLR a, F C b: Ul ICI..ldeI tem3Ul1 I C /__ P3 a- C1~z H L JS P31 a; b n eco ld leg te,,, ra, tr,-* j,*

1. For THERMAL POWER less than or equal to 30o RTP, 522oF TT 5582F,

2. For THERMAL POWER greater than 309t) RTr, 5354J tT t 5584.~

rfP, .i- 4.1- l -l 1 13n C nnn I I\,.,- I.* I. I I 1IV v .* *- ýJUvvv ýj jlIII .

APPLICABILITY: MODE 1.

NOTE---------------------

Pressurizer pressure limit does not apply during:

a. THERMAL POWER ramp > 5% RTP per minute; or

b. THERMAL POWER step > 10% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME.

A. Pressurizer A.1 Restore 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months pressure or RCS parameter(s) to flow rate not within limit.

within limits.

(continued)

SAN ONOFRE--UNIT 2 3.4-1 Amendment No. 27,14-9

RCS DNB (Pressure, Temperature, and Flow) Limits 3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action B.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and associated Completion Time of Condition A not met.

C. RCS cold leg C.1 Restore cold leg 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months temperature not temperature to within limits, within limits.

D. Required Action D.1 Reduce THERMAL 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and associated POWER to Completion Time of < 30% RTP.

Condition C not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Ve SR ify pressurizer pressure 3..1.112 swti te 1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or andmit<27 spelldin haOR. UJp SR 3.4.1.2 Verify KS cold leg temperature is withiý 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months th e Ili mitýs spec

ýifi e d *in e--0OL R.

1. For TIE"',MAL POWER less than.r equal to 30% RTn, o0 F Te 5WF-'

(continued)

SAN ONOFRE--UNIT 2 3.4-2 Amendment No. 127,149

RCS DNB (Pressure, Temperature, and Flow) Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEI LLANCE FREQUENCY SR 3.4.1.2 (continuied)

2. For TI[RMAL POWER greater than 30I RTIP,

NOTE----------------------

Required to be met in MODE I with all RCPs running.

SR 3.4.1.3 Vi R total flow rat is qreater than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or equal to the limm.ts specified in thef COR 396,000 gpffl.

SAN ONOFRE--UNIT 2 3.4-3 Amendment No. 127,14

Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.1.4 (Del eted) 5.7.1.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. Specification 3.1.1, "SHUTDOWN MARGIN (SDM) -Tavg

>200'F;"

2. Specification 3.1.2, "SHUTDOWN MARGIN (SDM) -Tavg

<200'F;"

3. Specification 3.1.4, "Moderator Temperature Coefficient;"

4. Specifica t ion 3.1.5, "Control Element Assembly (CEA)

Alignment;"

5. Specification 3.1.7, "Regulating CEA Insertion Limits;"

6. Specification 3.1.8, "Part Length Control Element-Assembly Insertion Limits;"

7. Specification 3.2.1, "Linear Heat Rate;"

8. Specification 3.2.4, "Departure From Nucleate Boiling Ratio;"

9. Specification 3.2.5, "Axial Shape Index;"

10. Specification 3.4.1, "RCS DNB (Pressure, Temperature, adFlow,)Limts II C9 +G.Specification 3.9.1, "Boron Concentration.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

(continued)

SAN ONOFRE--UNIT 2 5.0-26 Amendment No. 19-7,20

Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.1.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

1. CENPD-132P, "Calculative Methods for the C-E Large Break LOCA Evaluation Model"

2. CENPD-137P, "Calculative Methods for the C-E Small Break LOCA Evaluation Model"

3. CEN-356(V)-P-A, "Modified Statistical Combination of Uncertainties"

4. SCE-9801-P-A, "Reload Analysis Methodology for the San Onofre Nuclear Generating Station Units 2 and 3"

5. CEN-635(S), "Identification of NRC Safety Evaluation Report Limitations and/or Constraints on Reload Analysis Methodology"

6. Letter, dated May 16, 1986, G. W. Knighton (NRC) to K.

P. Baskin (SCE), "Issuance of Amendment No. 47 to Facility Operating License NPF-1O and Amendment No. 36 to Facility Operating License NPF-15," San Onofre Nuclear Generating Station Units 2 and 3 (Cycle..3,'SER)

7. Letter, dated January 9, 1985, G. W. Knighton (NRC) to K. P. Baskin, "Issuance of Amendment No. 30 to Facility Operating License NPF-1O and Amendment No. 19 to Facility Operating License NPF-15," San Onofre Nuclear Generating Station Units 2 and 3 (Cycle 2 SER)

8. "Implementation of ZIRLO M Cladding Material in CE Nuclear Power Fuel Assembly Designs," CENPD-404-P-A C. The core oDeratinq limits shall be determined assuming Go eration at RATED THERMAL POWER such that all6applicable limits Pe.g., tuel thermal-mechanical limits, core thermal hydraulic limits, Emergency Core Cooling System (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.7.1.6 REACTOR COOLANT SYSTEM (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a. RCS pressure and temperature limits for heatup, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

(continued)

SAN ONOFRE--UNIT 2 5.0-27 Amendment No. 197,199,2

ENCLOSURE 2 2b. Proposed Unit 3 Technical Specification Changes (Mark-Up)

RCS DNB (Pressure, Temperature, and Flow) Limits 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS DNB (Pressure, Temperature, and Flow) Limits LCO 3.4.1 RCS parameters for pressurizer pressure, cold leg temperature, and RCS total flow rate shall be within the limits specifiedi eCOL bel-w:

C1,. IC 3 IL.I Zl U iJl LUL-J fJ,.P 1 C1 1 I LL- J P 3 IU,

b. R*S cold l eg tempIr*ture

IT I

1. For T,,ERMAL POWER less than or equal to 30o RnTP 5224t*T, wý5582F,

2. For Tn'ERMAL POWER greater than 309o RTP, 5354 tF n IC, ~- -IXI nn iff nnn

t. I\%, t, UL[.I I I IUvY I UL. E; J-/UIUUU JlljIII.

APPLICABILITY: MODE 1.

NOTE---------------------

Pressurizer pressure limit does not apply during:

a. THERMAL POWER ramp > 5% RTP per minute; or

b. THERMAL POWER step > 10% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer A.1 Restore 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months pressure or RCS parameter(s) to flow rate not within limit.

within limits.

(continued)

SAN ONOFRE--UNIT 3 3.4-1 Amendment No. 16,141I

RCS DNB (Pressure, Temperature, and Flow) Limits 3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action B.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and associated Completion Time of Condition A not met.

C. RCS cold leg C.1 Restore cold leg 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months temperature not temperature to within limits, within limits.

D. Required Action D.1 Reduce THERMAL 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and associated POWER to Completion Time of < 30% RTP.

Condition C not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify ressurizer pressur is Wi *thih 't'e u *J*~- 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (li~m itts spe c if.i.e~d Ji~ t~he COLRj.

SR 3.4.1.2 Verify RCS cold leq temperatur is:withihn 1 (thle. :mi:t~s spreci'ffied iin the C;OLR.-.

1. For TnI[RMAL POWER Tlss than or equal to 3P,RT P , 5 F 558"Fed (conti nued)

SAN ONOFRE--UNIT 3 3.4-2 Amendment No. 116,141

RCS DNB (Pressure, Temperature, and Flow) Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.2 (eantinued)

2. Ir TIIERA*L POWER greater than 30J'RTr1, 5- Tc 558£k-F

NOTE----------------------

Required to be met in MODE 1 with all RCPs running.

SR 3.4.1.3 Verify RCS total flow rat is greater than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months i~nthW Ere eQu~al ýto týhelimýits sýpecif~ied COL, "R_3Gýo SAN ONOFRE--UNIT 3 3.4-3 Amendment No. 1-16,141

Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.1.4 (Deleted) 5.7.1.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. Specification 3.1.1, "SHUTDOWN MARGIN (SDM) - Tavg

>200°F;"

2. Specification 3.1.2, "SHUTDOWN MARGIN (SDM) - Tavg

<200'F;"

3. Specification 3.1.4, "Moderator Temperature Coefficient;"

4. Secifica t ion 3.1.5, "Control Element Assembly (CEA)

Alignment;"

5. Specification 3.1.7, "Regulating CEA Insertion Limits;"

6. Specification 3.1.8, "Part Length Control Element, Assembly Insertion Limits;"

7. Specification 3.2.1, "Linear Heat Rate;"

8. Specification 3.2.4, "Departure From Nucleate Boiling Ratio;"

9. Specification 3.2.5, "Axial Shape Index;"

1_0..* SaeCification 3.4.1, "RCS DNB IPressure, Temperatue adFlow) Limits;J 1-9.Specification

.- 3.9.1, "Boron Concentration."

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

(continued)

SAN ONOFRE--UNIT 3 5.0-26 Amendment No. 188,191

Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.1.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

1. CENPD-132P, "Calculative Methods for the C-E Large Break LOCA Evaluation Model"

2. CENPD-137P, "Calculative Methods for the C-E Small Break LOCA Evaluation Model"

3. CEN-356(V)-P-A, "Modified Statistical Combination of Uncertainties"

4. SCE-9801-P-A, "Reload Analysis Methodology for the San Onofre Nuclear Generating Station Units 2 and 3"

5. CEN-635(S), "Identification of NRC Safety Evaluation Report Limitations and/or Constraints on Reload Analysis Methodology"

6. Letter, dated May 16, 1986, G. W. Knighton (NRC) to K.

P. Baskin (SCE), "Issuance of Amendment No. 47 to Facility Operating License NPF-1O and Amendment No. 36 to Facility Operating License NPF-15," San Onofre.

Nuclear Generating Station Units 2 and 3 (Cycle&3 SER)

7. Letter, dated January 9, 1985, G. W. Knighton (NRC) to K. P. Baskin, "Issuance of Amendment No. 30 to Facility Operating License NPF-1O and Amendment No. 19 to Facility Operating License NPF-15," San Onofre Nuclear Generating Station Units 2 and 3 (Cycle 2 SER)

8. "Implementation of ZIRLOTM Cladding Material in CE Nuclear Power Fuel Assembly Designs," CENPD-404-P-A

c. The core operatinq limits shall be determineg (operation at RATED THERMAL POWER)such that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal hydraulic limits, Emergency Core Cooling System (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.7.1.6 REACTOR COOLANT SYSTEM (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a. RCS pressure and temperature limits for heatup, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

(continued)

SAN ONOFRE--UNIT 3 5.0-27 Amendment No. +/-8oo19,1-9-5

ENCLOSURE 3 3a. Proposed Unit 2 Technical Specifications

RCS DNB (Pressure, Temperature, and Flow) Limits 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS DNB (Pressure, Temperature, and Flow) Limits LCO 3.4.1 RCS parameters for pressurizer pressure, cold leg temperature, and RCS total flow rate shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1.

NOTE---------------------

Pressurizer pressure limit does not apply during:

a. THERMAL POWER ramp > 5% RTP per minute; or

b. THERMAL POWER step > 10% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer A.1 Restore 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months pressure or RCS parameter(s) to flow rate not within limit.

within limits.

(continued)

SAN ONOFRE--UNIT 2 3.4-1 Amendment No.

RCS DNB (Pressure, Temperature, and Flow) Limits 3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action B.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and associated Completion Time of Condition A not met.

C. RCS cold leg C.1 Restore cold leg 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months temperature not temperature to within limits, within limits.

D. Required Action D.1 Reduce THERMAL 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and associated POWER to Completion Time of < 30% RTP.

Condition C not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure is within the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months limits specified in the COLR.

SR 3.4.1.2 Verify RCS cold leg temperature is within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months the limits specified in the COLR.

(continued)

SAN ONOFRE--UNIT 2 3.4-2 Amendment No.

RCS DNB (Pressure, Temperature, and Flow) Limits 3.4.1 ACTIONS (continued)

SURVEILLANCE FREQUENCY

NOTE----------------------

Required to be met in MODE 1 with all RCPs running.

SR 3.4.1.3 Verify RCS total flow rate is greater than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or equal to the limits specified in the COLR.

SAN ONOFRE--UNIT 2 3.4-3 Amendment No.

Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.1.4 (Del eted) 5.7.1.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. Specification 3.1.1, "SHUTDOWN MARGIN (SDM) - Tavg

>200°F;'

2. Specification 3.1.2, "SHUTDOWN MARGIN (SDM) - T

<200' F; "

3. Specification 3.1.4, "Moderator Temperature Coefficient;"

4. SMecifica t ion 3.1.5, "Control Element Assembly (CEA)

Alignment;"

5. Specification 3.1.7, "Regulating CEA Insertion Limits;"

6. Specification 3.1.8, "Part Length Control Element Assembly Insertion Limits;"

7. Specification 3.2.1, "Linear Heat Rate;"

8. Specification 3.2.4, "Departure From Nucleate Boiling Ratio;"

9. Specification 3.2.5, "Axial Shape Index;"

10. Specification 3.4.1, "RCS DNB (Pressure, Temperature, and Flow) Limits;

11. Specification 3.9.1, "Boron Concentration."

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

(continued)

SAN ONOFRE--UNIT 2 5.0-26 Amendment No.

Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.1.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

1. CENPD-132P, "Calculative Methods for the C-E Large Break LOCA Evaluation Model"

2. CENPD-137P, "Calculative Methods for the C-E Small Break LOCA Evaluation Model"

3. CEN-356(V)-P-A, "Modified Statistical Combination of Uncertainties"

4. SCE-9801-P-A, "Reload Analysis Methodology for the San Onofre Nuclear Generating Station Units 2 and 3"

5. CEN-635(S), "Identification of NRC Safety Evaluation Report Limitations and/or Constraints on Reload Analysis Methodology"

6. Letter, dated May 16, 1986, G. W. Knighton (NRC) to K.

P. Baskin (SCE), "Issuance of Amendment No. 47 to Facility Operating License NPF-1O and Amendment No. 36 to Facility Operating License NPF-15," San Onofre Nuclear Generating Station Units 2 and 3 (Cyclei.3 SER)

7. Letter, dated January 9, 1985, G. W. Knighton (NRC) to K. P. Baskin, "Issuance of Amendment No. 30 to Facility Operating License NPF-1O and Amendment No. 19 to Facility Operating License NPF-15," San Onofre Nuclear Generating Station Units 2 and 3 (Cycle 2 SER)

8. "Implementation of ZIRLOM Cladding Material in CE Nuclear Power Fuel Assembly Designs," CENPD-404-P-A

c. The core operating limits shall be determined assuming operation at RATED THERMAL POWER such that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal hydraulic limits, Emergency Core Cooling System (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.7.1.6 REACTOR COOLANT SYSTEM (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a. RCS pressure and temperature limits for heatup, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

(continued)

SAN ONOFRE--UNIT 2 5.0-27 Amendment No.

ENCLOSURE 3 3b. Proposed Unit 3 Technical Specifications

RCS DNB (Pressure, Temperature, and Flow) Limits 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 RCS DNB (Pressure, Temperature, and Flow) Limits LCO 3.4.1 RCS parameters for pressurizer pressure, cold leg temperature, and RCS total flow rate shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1.

NOTE---------------------

Pressurizer pressure limit does not apply during:

a. THERMAL POWER ramp > 5% RTP per minute; or

b. THERMAL POWER step > 10% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer A.1 Restore 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months pressure or RCS parameter(s) to flow rate not within limit.

within limits.

(continued)

SAN ONOFRE--UNIT 3 3.4-1 Amendment No.

RCS DNB (Pressure, Temperature, and Flow) Limits 3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action B.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and associated Completion Time of Condition A not met.

C. RCS cold leg C.1 Restore cold leg 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months temperature not temperature to within limits, within limits.

D. Required Action D.1 Reduce THERMAL 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and associated POWER to Completion Time of < 30% RTP.

Condition C not met.

SURVEILLANCE REQUIREMENTS

.SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure is within the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months limits specified in the COLR.

SR 3.4.1.2 Verify RCS cold leg temperature is within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months the limits specified in the COLR.

(continued)

SAN ONOFRE--UNIT 3 3.4-2 Amendment No.

RCS DNB (Pressure, Temperature, and Flow) Limits 3.4.1 ACTIONS (continued)

SURVEILLANCE FREQUENCY

NOTE----------------------

Required to be met in MODE I with all RCPs running.

SR 3.4.1.3 Verify RCS total flow rate is greater than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or equal to the limits specified in the COLR.

SAN ONOFRE--UNIT 3 3.4-3 Amendment No.

Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.1.4 (Deleted) 5.7.1.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. Specification 3.1.1, "SHUTDOWN MARGIN (SDM) - Tav9

>200°F;"

2. Specification 3.1.2, "SHUTDOWN MARGIN (SDM) - Tavg

200'F;"

3. Specification 3.1.4, "Moderator Temperature Coefficient;"

4. Specifica t ion 3.1.5, "Control Element Assembly (CEA)

Alignment;"

5. Specification 3.1.7, "Regulating CEA Insertion Limits;"

6. Specification 3.1.8, "Part Length Control Element Assembly Insertion Limits;"

7. Specification 3.2.1, "Linear Heat Rate;"

8. Specification 3.2.4, "Departure From Nucleate Boiling Ratio;"

9. Specification 3.2.5, "Axial Shape Index;"

10. Specification 3.4.1, "RCS DNB (Pressure, Temperature, and Flow) Limits;

11. Specification 3.9.1, "Boron Concentration."

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

(continued)

SAN ONOFRE--UNIT 3 5.0-26 Amendment No.

Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.1.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

1. CENPD-132P, "Calculative Methods for the C-E Large Break LOCA Evaluation Model"

2. CENPD-137P, "Calculative Methods for the C-E Small Break LOCA Evaluation Model"

3. CEN-356(V)-P-A, "Modified Statistical Combination of Uncertainties"

4. SCE-9801-P-A, "Reload Analysis Methodology for the San Onofre Nuclear Generating Station Units 2 and 3"

5. CEN-635(S), "Identification of NRC Safety Evaluation Report Limitations and/or Constraints on Reload Analysis Methodology"

6. Letter, dated May 16, 1986, G. W. Knighton (NRC) to K.

P. Baskin (SCE), "Issuance of Amendment No. 47 to Facility Operating License NPF-1O and Amendment No. 36 to Facility Operating License NPF-15," San Onofre Nuclear Generating Station Units 2 and 3 (Cycler:3 SER)

7. Letter, dated January 9, 1985, G. W. Knighton (NRC) to K. P. Baskin, "Issuance of Amendment No. 30 to Facility Operating License NPF-1O and Amendment No. 19 to Facility Operating License NPF-15," San Onofre Nuclear Generating Station Units 2 and 3 (Cycle 2 SER)

8. "Implementation of ZIRLOTM Cladding Material in CE Nuclear Power Fuel Assembly Designs," CENPD-404-P-A

c. The core operating limits shall be determined assuming operation at RATED THERMAL POWER such that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal hydraulic limits, Emergency Core Cooling System (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.7.1.6 REACTOR COOLANT SYSTEM (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a. RCS pressure and temperature limits for heatup, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

(continued)

SAN ONOFRE--UNIT 3 5.0-27 Amendment No.

ENCLOSURE 4 Proposed Changes to Unit 2 Technical Specification Bases Pages (For information only - typical for both Units 2 and 3)

RCS DNB (Pressure, Temperature, and Flow) Limits B 3.4.1 BASES APPLICABLE within the limits of LCO 3.1.7, "Regulating CEA Insertion SAFETY ANALYSES Limits"; LCO 3.1.8, "Part Length CEA Insertion Limits";

(continued) LCO 3.2.3, "AZIMUTHAL POWER TILT (Tq)"; and LCO 3.2.5, "AXIAL SHAPE INDEX (ASI)". The safety analyses are performed over the following range of initial values: RCS pressure 2000 - 2300 psia, core inlet temperature 533 -

560'F (for > 30% power), and 520 - 560'F (for

30% power) and reactor vessel inlet coolant volumetric flow rate

>- 95%.

The RCS Pressure, Temperature, and Flow limits satisfy Criterion 2 of the NRC Policy Statement.

LCO This LCO specifies limits on the monitored process variables-RCS pressurizer pressure, RCS cold leg temperature [and RCS total flow rate)- to ensure that the core operates within These the limits assu-me 1,11 3es.......................

variables ar on:,:for ithei niplant nei ii......

1...

..... th1e COsafety LR t Drvd prating and analysis flexibiliýtyfrom cyclemto]

(ccle. Operating witin ese limits will result in meeting the DNBR criterion in the event of a DNB limited transient.

The LCO numerical values for pressure-a-d temperaturc*"

low rate s ecified in the COLR are given for the measurement location-but hveu not been adjusted for instrument error. The uncertainties for pressure and temperature are accounted for in the CPC and COLSS overall uncertainty analyses The RCS flow uncertainty must be applied to the value stated in this LCO.

APPLICABILITY In MODE 1, the limits on RCS pressurizer pressure, RCS cold leg temperature, and RCS flow rate must be maintained during steady state operation in order to ensure that DNBR criteria will be met in the event of an unplanned loss of forced coolant flow or other DNB limited transient. In all other MODES, the power level is low enough so that DNBR is not a concern.

A Note has been added to indicate the limit on pressurizer pressure may be exceeded during short term operational transients such as a THERMAL POWER ramp increase of > 5% RTP per minute or a THERMAL POWER step increase of > 10% RTP.

(conti nued)

SAN ONOFRE--UNIT 2 B 3.4-2 Amendment No. +2-i n2/24/-99

v t e Letter Sequence Request
TAC:MD9162, Relocate DNB Parameters to the Colr (Approved, Closed)
Initiation Request Acceptance Administration Questions Answers Results Approval Other: ML091200060
MONTHYEAR2008-07-23 [Table View]

ML081830515

Text

Subject:

Dear Sir or Madam:

Enclosures:

1.0 DESCRIPTION

2.0 PROPOSED CHANGE

3.0 BACKGROUND

4.0 TECHNICAL ANALYSIS

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