ML043510203

Proposed Change Number (PCN) 550 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Monitors Using the Consolidated Line Item Improvement Process

ML043510203
Person / Time
Site:	San Onofre
Issue date:	12/10/2004
From:	Nunn D Southern California Edison Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML043510203 (28)

Text

SOUTHERN CALIFORNIA Li n I

c nIr 2g Dwight E.

Nunn

_E L}DISJONI Vice President An EDISON IWTERNATIONALM Company December 10, 2004 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

SUBJECT:

SAN ONOFRE NUCLEAR GENERATING STATION, UNITS 2 AND 3 DOCKET NOs. 50-361 and 50-362 PROPOSED CHANGE NUMBER (PCN) 550 APPLICATION FOR TECHNICAL SPECIFICATION IMPROVEMENT TO ELIMINATE REQUIREMENTS FOR HYDROGEN MONITORS USING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS

Dear Sir or Madam:

Pursuant to 10 CFR 50.90, Southern California Edison (SCE) hereby requests an amendment to the Technical Specifications (TS) for the San Onofre Nuclear Generating Station, Units 2 and 3.

The proposed amendment will delete the TS requirements related to hydrogen monitors. The proposed TS change supports implementation of the revisions to 10 CFR 50.44, "Standards for Combustible Gas Control System in Light-Water-Cooled Power Reactors," that became effective on October 16, 2003. The changes are consistent with Revision 1 of NRC-approved Industry/Technical Specification Task Force (TSTF)

Standard Technical Specification Change Traveler, TSTF-447, "Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors." The availability of this TS improvement was announced in the Federal Register on September 25, 2003 as part of the consolidated line item improvement process (CLIIP). provides a description of the proposed change, the requested confirmation of applicability, and plant-specific verifications and commitments.

Attachments 2 and 4 provide the existing TS pages marked-up to show the proposed change. Attachments 3 and 5 provide revised, clean TS pages. Implementation of TSTF-447 also involves various changes to the TS Bases. The TS Bases changes will be submitted with a future update in accordance with TS 5.4.4, "Technical Specifications (TS) Bases Control."

SCE requests approval of the proposed License Amendment by January 3, 2006, with the amendment being implemented within 60 days of approval of this amendment request.

P.O. Box 128 San Clemente. CA 92674-0128 949-368-1480 Fax 949-368-1490

Document Control Desk December 10, 2004 In accordance with 10 CFR 50.91, a copy Of this application, with attachments, is being provided to the designated California State Official.

If You should have any questions regarding this submittal, please contact Mr. Jack Rainsberry at 949-368-7420.

Sincerely,

Enclosures:

1. Notarized affidavits

2. Licensee's evaluation of the proposed changes Attachments:

1. Description and Assessment

2. Proposed Technical Specification Changes, Unit 2

3. Revised Technical Specification Pages, Unit 2

4. Proposed Technical Specification Changes, Unit 3

5. Revised Technical Specification Pages, Unit 3 cc: B. S. Mallett, Regional Administrator, NRC Region IV, B. M. Pham, NRC Project Manager, San Onofre Units 2 and 3 C. C. Osterholtz, NRC Senior Resident Inspector, San Onofre Units 2 and 3 S. Y. Hsu, Department of Health Services, Radiologic Health Branch Page 1 of 2 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Application of SOUTHERN CALIFORNIA EDISON COMPANY, ETAL. fora Class 103 License to Acquire, Possess, and Use A Utilization Facility as Part of Unit No.2 of the San Onofre Nuclear Generating Station

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Docket No. 50-361 Amendment Application No. 228 SOUTHERN CALIFORNIA EDISON COMPANY, et al. pursuant to 10CFR50.90, hereby submit Amendment Application No. 228. This amendment application consists of Proposed Change Number (PCN) 550 to Facility Operating License NPF-10. PCN-550 is a request to delete the requirements related to hydrogen monitors in Technical Specification (TS) 3.3.11, "Post Accident Monitoring Instrumentation," for San Onofre Nuclear Generating Station Unit 2. The availability of this TS improvement was announced by the Nuclear Regulatory Commission in the Federal Register on September 25, 2003 as part of the consolidated line item improvement process (CLIIP).

State of California County of San Diego Subscribed and sworn to (or affirmed) before me this

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7 Commisston # 1295266 r Notary Pubilc - Colifornlo f 1 AWCSon Diego County

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Enclosure I Page 2 of 2 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Application of SOUTHERN CALIFORNIA EDISON COMPANY, ET AL. for a Class 103 License to Acquire, Possess, and Use A Utilization Facility as Part of Unit No. 3 of the San Onofre Nuclear Generating Station

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Docket No. 50-362 Amendment Application No. 212 SOUTHERN CALIFORNIA EDISON COMPANY, et al. pursuant to 10CFR50.90, hereby submit Amendment Application No. 212. This amendment application consists of Proposed Change Number (PCN) 550 to Facility Operating License NPF-15. PCN-550 is a request to delete the requirements related to hydrogen monitors in Technical Specification (TS) 3.3.11, NPost Accident Monitoring Instrumentation," for San Onofre Nuclear Generating Station Unit 3. The availability of this TS improvement was announced by the Nuclear Regulatory Commission in the Federal Register on September 25, 2003 as part of the consolidated line item improvement process (CLIIP).

State of California County of San Diego Subscribed and sworn to (or affirmed) before me this J 0 day of bec'.

,2004

--Vice PresidentV

~FRANCES Ml. THURBER Commisslon $ 1295266 Notary Public - Califonia I San Diego County l

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ATTACHMENT I DESCRIPTION AND ASSESSMENT

1.0 INTRODUCTION

The proposed License amendment deletes Technical Specification references to the hydrogen monitors in Technical Specification (TS) 3.3.11, 'Post Accident Monitoring Instrumentation (PAMI).' The proposed TS changes support implementation of the revisions to 10 CFR 50.44, "Standards for Combustible Gas Control System in Light-Water-Cooled Power Reactors," that became effective on October 16, 2003. The deletion of references to hydrogen monitors resulted in numbering and formatting changes to other TS, which were otherwise unaffected by this proposed amendment.

The changes are consistent with Revision 1 of NRC-approved Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-447, "Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors.' The availability of this TS improvement was announced in the Federal Register on September 25, 2003 as part of the consolidated line iem improvement process (CLIIP).

2.0 DESCRIPTION

OF PROPOSED AMENDMENT Consistent with the NRC-approved Revision 1 of TSTF-447, the proposed TS changes include:

TS 3.3.11, Condition D Inoperable Hydrogen Monitors Deleted Table 3.3.11-1 Item 10, Containment Hydrogen Deleted Monitors Other TS changes included in this application are limited to renumbering and formatting changes that resulted directly from the deletion of the above requirements related to hydrogen monitors.

As described in NRC-approved Revision 1 of TSTF-447, the changes to TS requirements result in changes to various TS Bases sections. The TS Bases changes will be submitted with a future update in accordance with TS 5.4.4, "Technical Specifications (TS) Bases Control."

3.0 BACKGROUND

The background for this application is adequately addressed by the NRC Notice of Availability published on September 25, 2003 (68 FR 55416), TSTF-447, the documentation associated with the 10 CFR 50.44 rulemaking, and other related documents.

4.0 REGULATORY REQUIREMENTS AND GUIDANCE The applicable regulatory requirements and guidance associated with this application are adequately addressed by the NRC Notice of Availability published on September 25, 2003 (68 FR 55416), TSTF-447, the documentation associated with the 10 CFR 50.44 rulemaking, and other related documents.

Page 1 of 3

5.0 TECHNICAL ANALYSIS

Southern California Edison (SCE) has reviewed the safety evaluation (SE) published on September 25, 2003 (68 FR 55416), as part of the CLIIP Notice of Availability. This verification included a review of the NRC staff's SE, as well as the supporting information provided to support TSTF-447. SCE has concluded that the justifications presented in the TSTF proposal and the SE prepared by the NRC staff are applicable to San Onofre Nuclear Generating Station, Units 2 and 3 (SONGS 2 & 3), and justify this amendment for the incorporation of the changes to the SONGS 2

& 3 TS.

6.0 REGULATORY ANALYSIS

A description of this proposed change and its relationship to applicable regulatory requirements and guidance was provided in the NRC Notice of Availability published on September 25, 2003 (68 FR 55416), TSTF-447, the documentation associated with the 10 CFR 50.44 rulemaking, and other related documents.

6.1 Verification and Commitments As discussed in the model SE published in the Federal Register on September 25, 2003 (68 FR 55416), for this TS improvement, SCE is making the following verifications and regulatory commitments:

1.

SCE has verified that a hydrogen monitoring system capable of diagnosing beyond design-basis accidents is installed at SONGS 2 & 3 and is making a regulatory commitment to maintain that capability. The hydrogen monitors will be included in the Licensee Controlled Specifications. This regulatory commitment will be implemented within 60 days of approval of this amendment request.

2.

SONGS 2 & 3 do not have Inerted containments.

7.0 NO SIGNIFICANT HAZARDS CONSIDERATION Southern California Edison (SCE) has reviewed the proposed no significant hazards consideration determination published on September 25, 2003 (68 FR 55416) as part of the CLIIP. SCE has concluded that the proposed determination presented in the notice is applicable to San Onofre Nuclear Generating Station Units 2 and 3, and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91 (a).

8.0 ENVIRONMENTAL EVALUATION Southern California Edison (SCE) has reviewed the environmental evaluation included in the model SE published on September 25, 2003 (68 FR 55416) as part of the CLIIP. SCE has concluded that the staffs findings presented in that evaluation are applicable to San Onofre Nuclear Generating Station Units 2 and 3, and the evaluation is hereby incorporated by reference for this application.

Page 2 of 3

9.0 PRECEDENT This application is being made in accordance with the CLIIP. With the exception noted below, Southern California Edison (SCE) is not proposing variations or deviations from the TS changes described in TSTF-447 or the NRC staff's model SE published on September 25, 2003 (68 FR 55416).

EXCEPTION:

SCE is proposing not to renumber the function list in Table 3.3.11-1. SCE is making this exception in order to reduce the possibility of errors arising where references to the functions are made by number.

10.0 REFERENCES

Federal Register Notice: Notice of Availability of Model Application Concerning Technical Specification Improvement To Eliminate Hydrogen Recombiner Requirement, and Relax the Hydrogen and Oxygen Monitor Requirements for Light Water Reactors Using the Consolidated Line Item Improvement Process, published September 25, 2003 (68 FR 55416).

Page 3 of 3 ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION CHANGES, UNIT 2 (MARK-UP)

PAM Instrumentation 3.3.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

NOTE C.1 Restore one channel 7 days Not applicable to to OPERABLE status.

hydrogen monitor channels.

One or more Functions with two required channels inoperable.

D. Two hydrogen monitor D.1 Restore one hydrogen 92-hours channels inoperable.

monitor channel to ED.

Required channel of ED.1 Restore required channel 7 days Functions 18, 21, 24, to OPERABLE status.

or 25 inoperable.

FE.

Required Action and FE.1 Enter the Condition Immediately associated Completion referenced in Time of Condition CT Table 3.3.11-1 for the O or ED not met.

channel.

GF. As required by CGF.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 /> Required Action FE.1 and referenced in AND Table 3.3.11-1.

F.

3.12 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

• G. As required by

+G.1 Prepare and submit a 30 days Required Action fE.1 Special Report to the and referenced in NRC in accordance with Table 3.3.11-1.

Specification 5.7.2.

SAN ONOFRE--UNIT 2 3.3-45 Amendment No. +-12

PAM Instrumentation 3.3.11 SURVEILLANCE REQUIREMENTS

---

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

These SRs apply to each PAMI Function in Table 3.3.11-1, with exceptions noted.

SURVEILLANCE FREQUENCY SR 3.3.11.1 Perform CHANNEL CHECK for Function 9.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.11.2 Perform CHANNEL CHECK for each required 31 days instrumentation channel, except Function 9, that is normally energized.

SR 3.3.11.3 Perform CHANNEL FUNCTIONAL TEST for 31 days function 9.

SR 3.3.11.4 Perform CHANNEL CALIBRATION, for functions 18 months..

2,3,14,15,16,17, and 20.

SR 3.3.11.5 Perform CHANNEL CALIBRATION for functions 24 months 1,4,5,6,7,8,9, i-G-11,12,13,18, 19,21,22,23,24,25,26, and 27.

SAN ONOFRE--UNIT 2 3.3-46 Amendment No. 2-7-1-76

PAM Instrumentation 3.3.11 Table 3.3.11-1 (page 1 of 1)

Post Accident Monitoring Instrumentation CONDITIONS REFERENCED FROM REQUIRED FUNCTION REQUIRED CHANNELS ACTION F.1

1. Excore Neutron Flux 2

GF

2. Reactor Coolant System Hot Leg Temperature 2 (1 per steam GF generator)

3. Reactor Coolant System Cold Leg Temperature 2 (1 per steam OF generator)

4. Reactor Coolant System Pressure (wide range) 2 GF

5. Reactor Vessel Water Level 2(d)

6. Containment Water Level (wide range) 2 GF

7. Containment Pressure (wide range) 2 GF

8. Containment Isolation Valve Position 2 per penetrf flow F

9. Containment Area Radiation (high range) 2 1G

10. DeletedCz-t--n--

Hdrogen Monitor; G

11. Pressurizer Level 2

GF

12. Steam Generator Water Level (wide range) 2 per steam generator GF

13. Condensate Storage Tank Level 2

GF

14. Core Exit Temperature-Quadrant 1 2(c)

GF

15. Core Exit Temperature-Quadrant 2 2(c)

GF

16. Core Exit Temperature-Quadrant 3 2(c)

17. Core Exit Temperature-Quadrant 4 2(c)

GF

18. Auxiliary Feedwater Flow 1 per steam generator GF

19. Containment Pressure (narrow range) 2 GF

20. Reactor Coolant System Subcooling Margin Monitor 2

GF

21.

Pressurizer Safety Valve Position Indication 1 per valve GF

22. Containment Temperature 2

GF

23.

Containment Water Level (narrow range) 2 GF

24.

HPSI Flow Cold Leg 1 per cold leg OF

25. HPSI Flow Hot Leg 1 per hot leg GF

26. Steam Line Pressure 2 per steam generator

27.

Refueling Water Storage Tank Level 2

GF (a) Not required for isolation valves whose associated penetration is isolated by at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

(c) A channel consists of two or more core exit thermocouples.

(d) A channel consists of eight sensors in a probe. A channel is OPERABLE if four or more sensors, one sensor in the upper head and three sensors in the lower head are OPERABLE.

SAN ONOFRE--UNIT 2

3. 3-47 Amendment No. 127,130, 147

Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.2 Special Reports Special Reports may be required covering inspection, test, and maintenance activities. These special reports are determined on an individual basis for each unit and their preparation and submittal are designated in the Technical Specifications.

Special Reports shall be submitted to the U. S. Nuclear Regulatory Commission, Attention: Document Control Desk, Washington, D. C.

20555, with a copy to the Regional Administrator of the Regional Office of the NRC, in accordance with 10 CFR 50.4 within the time period specified for each report.

The following Special Reports shall be submitted:

a.

When a pre-planned alternate method of monitoring post-accident instrumentation functions is required by Condition B or Condition fIG of LCO 3.3.11, a report shall be submitted within 30 days'from the time the action is required. The report shall outline the action taken, the cause of the inoperability, and the plans and schedule for restoring-the instrumentation channels of the function to OPERABLE status.

b.

Any abnormal degradation of the containment structure detected during the tests required by the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be reported to the NRC within 30 days. The report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the corrective action taken.

c.

Following each inservice inspection of steam generator (SG) tubes, in accordance with the SG Tube Surveillance Program, the number of tubes plugged and tubes sleeved in each SG shall be reported to the NRC within 15 days.

The complete results of the SG tube inservice inspection shall be submitted to the NRC within 12 months following the completion of the inspection.

The report shall include:

1.

Number and extent of tubes and sleeves inspected, and

2.

Location and percent of wall-thickness penetration for each indication of an imperfection, and

3.

Identification of tubes plugged and tubes sleeved.

(continued)

SAN ONOFRE--UNIT 2 5.0-30 Amendment No. 127140 ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATION PAGES, UNIT 2

PAM Instrumentation 3.3.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more Functions C.1 Restore one channel 7 days with two required to OPERABLE status.

channels inoperable.

D. Required channel of D.1 Restore required 7 days Functions 18, 21, 24, channel to OPERABLE or 25 inoperable.

status.

E. Required Action and E.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C Table 3.3.11-1 for or D not met.

the channel.

F. As required by F.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 /> Required Action E.1 and referenced in AND Table 3.3.11-1.

F.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> G. As required by G.1 Prepare and submit a 30 days Required Action E.1 Special Report to the and referenced in NRC in accordance Table 3.3.11-1.

with Specification 5.7.2.

I SAN ONOFRE--UNIT 2

3.

3-45 Amendment No.

PAM Instrumentation 3.3.11 SURVEILLANCE REQUIREMENTS NOTE---------- _- _-

These SRs apply to each PAMI Function in Table 3.3.11-1, with exceptions noted.

SURVEILLANCE FREQUENCY SR 3.3.11.1 Perform CHANNEL CHECK for Function 9.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.11.2 Perform CHANNEL CHECK for each required 31 days instrumentation channel, except Function 9, that is normally energized.

SR 3.3.11.3 Perform CHANNEL FUNCTIONAL TEST for 31 days function 9.

SR 3.3.11.4 Perform CHANNEL CALIBRATION, for functions 18 months~

2,3,14,15,16,17, and 20.

SR 3.3.11.5 Perform CHANNEL CALIBRATION for functions 24 months 1,4,5,6,7,8,9,11,12,13,18, 19,21,22,23,24,25,26, and 27.

I SAN ONOFRE--UNIT 2 3.3-46 Amendment No.

PAM Instrumentation 3.3.11 Table 3.3.11-1 (page 1 of 1)

Post Accident Monitoring Instrumentation CONDITIONS REFERENCED FROM REQUIRED FUNCTION REQUIRED CHANNELS ACTION F.1

1. Excore Neutron Flux 2

F

2. Reactor Coolant System Hot Leg Temperature 2 (1 per steam F

generator)

3. Reactor Coolant System Cold Leg Temperature 2 (1 per steam F

generator)

4. Reactor Coolant System Pressure (wide range) 2 F

5. Reactor Vessel Water Level 2(d)

G

6. Containment Water Level (wide range) 2 F

7. Containment Pressure (wide range) 2 F

8. Containment Isolation Valve Position 2 per penetratin flow F

path a b

9. Containment Area Radiation (high range) 2 G

10.

Deleted

11.

Pressurizer Level 2

F

12.

Steam Generator Water Level (wide range) 2 per steam generator F

13.

Condensate Storage Tank Level 2

F

14.

Core Exit Temperature -Quadrant 1 2(c)

F

15.

Core Exit Temperature - Quadrant 2 2(c)

F

16.

Core Exit Temperature -Quadrant 3 2(c)

F

17.

Core Exit Temperature -Quadrant 4 2(c)

F

18.

Auxiliary Feedwater Flow 1 per steam generator F

19. Containment Pressure (narrow range) 2 F

20.

Reactor Coolant System Subcooling Margin 2

F Monitor

21.

Pressurizer Safety Valve Position Indication 1 per valve F

22.

Containment Temperature 2

F

23.

Containment Water Level (narrow range) 2 F

24.

HPSI Flow Cold Leg I per cold leg F

25.

HPSI Flow Hot Leg 1 per hot leg F

26.

Steam Line Pressure 2 per steam generator F

27.

Refueling Water Storage Tank Level 2

F (a) Not required for isolation valves whose associated penetration is isolated by at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

(c) A channel consists of two or more core exit thermocouples.

(d) A channel consists of eight sensors in a probe. A channel is OPERABLE if four or more sensors, one SAN ONOFRE--UNIT 2

3. 3-47 Amendment No.

Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.2 Special Reports Special Reports may be required covering inspection, test, and maintenance activities. These special reports are determined on an individual basis for each unit and their preparation and submittal are designated in the Technical Specifications.

Special Reports shall be submitted to the U. S. Nuclear Regulatory Commission, Attention: Document Control Desk, Washington, D. C.

20555, with a copy to the Regional Administrator of the Regional Office of the NRC, in accordance with 10 CFR 50.4 within the time period specified for each report.

The following Special Reports shall be submitted:

a.

When a pre-planned alternate method of monitoring post-accident instrumentation functions is required by Condition B or Condition G of LCO 3.3.11, a report shall be submitted within 30 days from the time the action is required.

The report shall outline the action taken, the cause of the inoperability, and the plans and schedule for restoring-the instrumentation channels of the function to OPERABLE status.

b.

Any abnormal degradation of the containment structure detected during the tests required by the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be reported to the NRC within 30 days. The report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the corrective action taken.

c.

Following each inservice inspection of steam generator (SG) tubes, in accordance with the SG Tube Surveillance Program, the number of tubes plugged and tubes sleeved in each SG shall be reported to the NRC within 15 days. The complete results of the SG tube inservice inspection shall be submitted to the NRC within 12 months following the completion of the inspection.

The report shall include:

1.

Number and extent of tubes and sleeves inspected, and

2.

Location and percent of wall-thickness penetration for each indication of an imperfection, and

3.

Identification of tubes plugged and tubes sleeved.

(continued)

SAN ONOFRE--UNIT 2 5.0-30 Amendment No.

ATTACHMENT 4 PROPOSED TECHNICAL SPECIFICATION CHANGES, UNIT 3 (MARK-UP)

PAM Instrumentation 3.3.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

-NOTE C.1 Restore one channel 7 days Not applicable to to OPERABLE status.

hydrogen monitor One or more Functions with two required channels inoperable.

D. Two hydrogen monitor D.7 Restore one hydrgen 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> channels inoperable.

monitor Thannel to OPERABLE status.

ED. Required channel of ED.1 Restore required 7 days Functions 18, 21, 24, channel to OPERABLE or 25 inoperable.

status.

fE. Required Action and fE.1 Enter the Condition Immediately associated Completion referenced in Time of Condition CT Table 3.3.11-1 for D or ED not met.

the channel.

GF. As required by GF.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 /> Required Action fE.1 and referenced in AND Table 3.3.11-1.

GF.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />

• G. As required by 14G.1 Prepare and submit a 30 days Required Action fE.1 Special Report to the and referenced in NRC in accordance Table 3.3.11-1.

with Specification 5.7.2.

SAN ONOFRE--UNIT 3 3.3-45 Amendment No. 4 PAM Instrumentation 3.3.11 SURVEILLANCE REQUIREMENTS

---

 :-----------NOTE---------

These SRs apply to each PAMI Function in Table 3.3.11-1, with exceptions noted.

SURVEILLANCE FREQUENCY SR 3.3.11.1 Perform CHANNEL CHECK for Function 9.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.11.2 Perform CHANNEL CHECK for each required 31 days instrumentation channel, except Function 9, that is normally energized.

SR 3.3.11.3 Perform CHANNEL FUNCTIONAL TEST for 31 days function 9.

SR 3.3.11.4 Perform CHANNEL CALIBRATION, for functions 18 months 2,3,14,15,16,17, and 20.

SR 3.3.11.5 Perform CHANNEL CALIBRATION for functions 24 months 1,4,5,6,7,8,9,+5,11,a2,13,18, 19,21,22,23,24,25,26, and 27.

SAN ONOFRE--UNIT 3 3.3-46 Amendment No. 116,167

PAM Instrumentation 3.3.11 Table 3.3.11-1 (page 1 of 1)

Post Accident Monitoring Instrumentation FUNCTION REQUIRED CHANNELS

1. Excore Neutron Flux

2. Reactor Coolant System Hot Leg Temperature

3. Reactor Coolant System Cold Leg Temperature

4. Reactor Coolant System Pressure (wide range)

5. Reactor Vessel Water Level

6. Containment Water Level (wide range)

7. Containment Pressure (wide range)

8. Containment Isolation Valve Position 2

2 (1 per steam generator) 2 (1 per steam generator) 2 2(d) 2 2

2 per penetratsrn flow 2patha 2

CONDITIONS REFERENCED FROM REQUIRED ACTION F.1 GF GF 4F GF GF GF GF 9.

10.

11.

12.

13.

14.

15.

16.

17.

18.

19.

20.

Containment Area Radiation (high range)

Deletd~onlinmntbHdregen Monitors Pressurizer Level Steam Generator Water Level (wide range)

Condensate Storage Tank Level Core Exit Temperature -Quadrant 1

Core Exit Temperature-Quadrant 2 Core Exit Temperature-Quadrant 3 Core Exit Temperature-Quadrant 4 Auxiliary Feedwater Flow Containment Pressure (narrow range)

Reactor Coolant System Subcooling Margin Monitor 2

2 per steam generator 2

2(c) 2(c) 2(c) 2(c) 1 per steam generator 2

2

• G 6

4.

GF GF 4.

4.

4F

21.

Pressurizer Safety Valve Position Indication 1 per valve GF

22.

Containment Temperature 2

23.

Containment Water Level (narrow range) 2

24.

HPSI Flow Cold Leg 1 per cold leg GF

25.

HPSI Flow Hot Leg 1 per hot leg GF

26.

Steam Line Pressure 2 per steam generator GF

27.

Refueling Water Storage Tank Level 2

4.

(a) Not required for isolation valves whose associated penetration is isolated by at least one closed and de-activated automatic valve. closed manual valve, blind flange, or check valve with flow through the valve secured.

(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

(c) A channel consists of two or more core exit thermocouples.

SAN ONOFRE--UNIT 3

3. 3-47 Amendment No. 116,-119-, 139

Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.2 Special Reports Special Reports may be required covering inspection, test, and maintenance activities.

These special reports are determined on an individual basis for each unit and their preparation and submittal are designated in the Technical Specifications.

Special Reports shall be submitted to the U. S. Nuclear Regulatory Commission, Attention: Document Control Desk, Washington, D. C.

20555, with a copy to the Regional Administrator of the Regional Office of the NRC, in accordance with 10 CFR 50.4 within the time period specified for each report.

The following Special Reports shall be submitted:

a.

When a pre-planned alternate method of monitoring post-accident instrumentation functions is required by Condition B or Condition 14G of LCO 3.3.11, a report shall be submitted within 30 days from the time the action is required. The report shall outline the action taken, the cause of the inoperability, and the plans and schedule for restoring-the instrumentation channels of the function to OPERABLE status.

b.

Any abnormal degradation of the containment structure detected during the tests required by the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be reported to the NRC within 30 days.

The report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the corrective action taken.

c.

Following each inservice inspection of steam generator (SG) tubes, in accordance with the SG Tube Surveillance Program, the number of tubes plugged and tubes sleeved in each SG shall be reported to the NRC within 15 days.

The complete results of the SG tube inservice inspection shall be submitted to the NRC within 12 months following the completion of the.

inspection.

The report shall include:

1.

Number and extent of tubes and sleeves inspected, and

2.

Location and percent of wall-thickness penetration for each indication of an imperfection, and

3.

Identification of tubes plugged and tubes sleeved.

(continued)

SAN ONOFRE--UNIT 3 5.0-30 Amendment No. 116 132 ATTACHMENT 5 PROPOSED TECHNICAL SPECIFICATION PAGES, UNIT 3

PAM Instrumentation 3.3.11 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more Functions C.1 Restore one channel 7 days with two required to OPERABLE status.

channels inoperable.

D. Required channel of D.1 Restore required 7 days Functions 18, 21, 24, channel to OPERABLE or 25 inoperable.

status.

E. Required Action and E.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C Table 3.3.11-1 for or D not met.

the channel.

F. As required by F.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 /> Required Action E.1 and referenced in AND Table 3.3.11-1.

F.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> G. As required by G.1 Prepare and submit a 30 days Required Action E.1 Special Report to the and referenced in NRC in accordance Table 3.3.11-1.

with Specification 5.7.2.

SAN ONOFRE--UNIT 3 3.3-45 Amendment No.

PAM Instrumentation 3.3.11 SURVEILLANCE REQUIREMENTS

---

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

These SRs apply to each PAMI Function in Table 3.3.11-1, with exceptions noted.

SURVEILLANCE FREQUENCY SR 3.3.11.1 Perform CHANNEL CHECK for Function 9.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.11.2 Perform CHANNEL CHECK for each required 31 days instrumentation channel, except Function 9, that is normally energized.

SR 3.3.11.3 Perform CHANNEL FUNCTIONAL TEST for 31 days function 9.

SR 3.3.11.4 Perform CHANNEL CALIBRATION, for functions 18 months 2,3,14,15,16,17, and 20.

SR 3.3.11.5 Perform CHANNEL CALIBRATION for functions 24 months 1,4,5,6,7,8,9,11,12,13,18, 19,21,22,23,24,25,26, and 27.

I SAN ONOFRE--UNIT 3 3.3-46 Amendment No.

PAM Instrumentation 3.3.11 Table 3.3.11-1 (page 1 of 1)

Post Accident Monitoring Instrumentation CONDITIONS REFERENCED FROM REQUIRED FUNCTION REQUIRED CHANNELS ACTION F.1

1. Excore Neutron Flux 2

F

2. Reactor Coolant System Hot Leg Temperature 2 (1 per steam F

generator)

3. Reactor Coolant System Cold Leg Temperature 2 (1 per steam F

generator)

4. Reactor Coolant System Pressure (wide range) 2 F

5. Reactor Vessel Water Level 2(d)

G

6. Containment Water Level (wide range) 2 F

7. Containment Pressure (wide range) 2 F

8. Containment Isolation Valve Position 2 per penertr yn flow F

patha

9. Containment Area Radiation (high range) 2 G

10.

Deleted

11. Pressurizer Level 2

F

12. Steam Generator Water Level (wide range) 2 per steam generator F

13.

Condensate Storage Tank Level 2

F

14.

Core Exit Temperature-Quadrant 1 2(c)

F

15.

Core Exit Temperature-Quadrant 2 2(c)

F

16.

Core Exit Temperature-Quadrant 3 2(c)

F

17.

Core Exit Temperature-Quadrant 4 2(c)

F

18.

Auxiliary Feedwater Flow 1 per steam generator F

19.

Containment Pressure (narrow range) 2 F

20.

Reactor Coolant System Subcooling Margin 2

F Monitor

21.

Pressurizer Safety Valve Position Indication 1 per valve F

22.

Containment Temperature 2

F

23.

Containment Water Level (narrow range) 2 F

24.

HPSI Flow Cold Leg 1 per cold leg F

25.

HPSI Flow Hot Leg 1 per hot leg F

26.

Steam Line Pressure 2 per steam generator F

27.

Refueling Water Storage Tank Level 2

F (a) Not required for isolation valves whose associated penetration is isolated by at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

(c) A channel consists of two or more core exit thermocouples.

SAN ONOFRE--UNIT 3

3. 3-47 Amendment No.

Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.2 Special Reports Special Reports may be required covering inspection, test, and maintenance activities. These special reports are determined on an individual basis for each unit and their preparation and submittal are designated in the Technical Specifications.

Special Reports shall be submitted to the U. S. Nuclear Regulatory Commission, Attention: Document Control Desk, Washington, D. C.

20555, with a copy to the Regional Administrator of the Regional Office of the NRC, in accordance with 10 CFR 50.4 within the time period specified for each report.

The following Special Reports shall be submitted:

a.

When a pre-planned alternate method of monitoring post-accident instrumentation functions is required by Condition B or Condition G of LCO 3.3.11, a report shall be submitted within 30 days from the time the action is required. The report shall outline the action taken, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the function to OPERABLE status.

b.

Any abnormal degradation of the containment structure detected during the tests required by the Pre-Stressed Concrete Containment Tendon Surveillance Program shall be reported to the NRC within 30 days. The report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the corrective action taken.

c.

Following each inservice inspection of steam generator (SG) tubes, in accordance with the SG Tube Surveillance Program, the number of tubes plugged and tubes sleeved in each SG shall be reported to the NRC within 15 days.

The complete results of the SG tube inservice inspection shall be submitted to the NRC within 12 months following the completion of the inspection.

The report shall include:

1.

Number and extent of tubes and sleeves inspected, and

2.

Location and percent of wall-thickness penetration for each indication of an imperfection, and

3.

Identification of tubes plugged and tubes sleeved.

(continued)

SAN ONOFRE--UNIT 3 5.0-30 Amendment No.