DCL-05-023, Inservice Testing (IST) Program - Third Ten-Year Interval and IST Relief Requests

Inservice Testing (IST) Program - Third Ten-Year Interval and IST Relief Requests

ML050810609
Person / Time
Site:	Diablo Canyon
Issue date:	03/14/2005
From:	Jacobs D Pacific Gas & Electric Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
DCL-05-023, GL-89-004, NUREG-1482, OL-DPR-80, OL-DPR-82
Download: ML050810609 (133)

Text

Pacific Gasand Electric Company Donna Jacobs Diablo Canyon Power Plant Vice President P.0. Box 56 March 14, 2005 Nuclear Services Avila Beach, CA 93424 805.545.4600 PG&E Letter DCL-05-023 Fax: 805.545.4234 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Power Plants (DCPP) Units 1 and 2 Inservice Testinq (IST) Program - Third Ten-Year Interval and IST Relief Requests

Dear Commissioners and Staff:

Pursuant to 10 CFR 50.55a(f)(5)(i), the DCPP IST Program has been revised and is provided as the "Third Ten-Year Interval, Revision 0," in Enclosure 1. The IST Program incorporates the 2001 Edition with the 2002 and 2003 Addenda of the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) with 10 CFR 50.55a(b) approved Code Cases as applicable. Generic Letter 89-04, "Guidance on Developing Acceptable Inservice Testing Programs," approval of NUREG-1482, "Guidelines for Inservice Testing Programs at Nuclear Power Plants,"

regulatory positions are incorporated in the revised IST Program. The third ten-year Interval will begin January 1, 2006, and June 1, 2006, for Units 1 and 2, respectively.

Included in this submittal are two IST Requests for Relief from Code Requirements that were approved for use during the second ten-year interval. Enclosure 2 provides Relief Request No. P-RR1 (Table 1.1, pages 2 through 4) that was previously approved as P-RR4 by NRC letter dated February 25, 1998. Enclosure 3 provides Relief Request No. P-RR2 (Table 1.1, pages 5 and 6) that was previously approved as No. P-RR5 by NRC letter dated December 30,1998.

Sincerely, Donia Jacobs ddm/469 Enclosures cc: David L. Proulx, NRC Senior Resident Inspector Gregory M. Rueger 7A0°4-cc/enc: Paul R. Fox, American Nuclear Insurers Bruce S. Mallett, NRC Regional Administrator, Region IV Girija S. Shukla, NRC Project Manager A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Caltaway

• Comanche Peak

• Diablo Canyon

• Palo Verde

• South Texas Project

• Wolf Creek

Enclosure 1 PG&E Letter DCL-05-023 INSERVICE TESTING (IST) PROGRAM THIRD TEN-YEAR INTERVAL, REVISION 0 DIABLO CANYON POWER PLANTS UNIT 1 AND 2

Pacific Gas and Electric Company Revision 0 77 Beale Street January 7, 2005 San Francisco, California 94177 INSERVICE TESTING PROGRAM THIRD TEN-YEAR INTERVAL DIABLO CANYON POWER PLANT UNITS I AND 2 Pacific Gas and Electric Company P.O. Box 56 Avila Beach, California 93424 USNRC DOCKET NOS. 50-275/50-323 FACILITY OPERATING LICENSE NOS. DPR-80/82 COMMERCIAL OPERATION DATES: MAY 7, 1985/MARCH 13, 1986 Prepared by:

Reviewed by:

Approved:

Approved by:

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Pacific Gas and Electric Company Revision 0 77 Beale Street January 7, 2005 San Francisco, California 94177 INSERVICE TESTING PROGRAM PLAN THIRD TEN-YEAR INTERVAL INTRODUCTION This volume describes the Inservice Testing (IST) Program Plan for Diablo Canyon Power Plant's safety-related components (pumps and valves) which are classified ASME Code Class 1, Class 2, and Class 3.

This IST Program Plan complies with the requirements of 10 CFR Part 50.55a(a), Part 50.55a(b) (2), and Part 50.55a(f), effective (LATER), as follows:

10CFR50.55a(f) (1) - For a pressurized water-cooled nuclear facilities (PWR) whose construction permit was issued prior to January 1, 1971 (Unit l's was issued April 23, 1968 and Unit 2's was issued December 9, 1970), pumps and valves must meet the requirements of paragraphs (f) (4) and (5).

10CFR50.55a(f) (4) - Throughout the service life of a PWR, ASME Code Class 1, 2, or 3 pumps and valves must meet the ASME OM Code and Addenda that are incorporated by reference in paragraph (b) of this section, to the extent practical within the limitations of design, geometry and materials of construction of such components.

10CFR50.55a(b) (2) - ...references to Section XI of the ASME B&PV Code refer to Section XI, and include the 1970 Edition through the 1976 Winter Addenda, and the 1977 Edition (Division I) through the 2001 Addenda and editions through the 2002 and 2003 Addenda.

10CFR50.55a(f) (4) (ii) - Inservice tests conducted during successive 120-month intervals must comply with the requirements of the latest edition and addenda of the Code incorporated by reference in paragraph (b) of this section 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed in paragraph (b).

IOCFR50.55a(f) (4) (iv) - IST of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (b),

subject to the limitations and modifications listed in paragraph (b), and subject to Commission approval. Portions of editions or addenda may be used provided that all related requirement of the respective additions or addenda are met.

10CFR50.55a(f) (5) (i) - The IST program for a PWR must be revised, as necessary, to meet the requirements of paragraph (f) (4).

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Pacific Gas and Electric Company Revision 0 77 Beale Street January 7, 2005 San Francisco, California 94177 10 CFR Part 50.55a incorporated by reference the 2001 Edition and the 2002 and 2003 Addenda of the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code).

The initial testing interval for Unit 1 began May 7, 1985, and for Unit 2 began March 13, 1986, when the respective Units were placed into commercial operation.

The second ten-year interval began January 1, 1996 for Unit 1 and June 1, 1996 for Unit 2.

The third ten-year interval will begin on January 1, 2006 for Unit I and June 1, 2006 for Unit 2.

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Pacific Gas and Electric Company Revision 0 77 Beale Street January 7, 2005 San Francisco, California 94177 Where conformance with certain Code requirements is impractical, requests for relief, in accordance with 10CFR50.55a(a) (3) and 10CFR50.55a(f) (5), are included in each section with supporting information and proposed alternatives. Preservice tests, where required, have been completed. All preservice test data is available for review at the plant site.

ASME SECTION XI CODE BOUNDARY DRAWINGS The ASME Code Classification Boundary Drawings, PG&E Number 102028 (Unit 1) and 104628 (Unit 2),

are located in Section 2.0 of the Inservice Inspection (ISI) Program Plan. Regulatory Guide 1.261 was used as the governing document in setting up the Inservice Inspection and Testing Program (ISIT) boundary. The drawings show the Code Class 1, 2, and 3 systems and components subject to inservice inspection and testing requirements. Systems and components are identified by Code Class and are color coded as applicable to indicate exemptions from various code requirements 2 . These drawings are extracted from the piping schematics (P&ID's) for the plant that are contained in Section 3.2 of the FSAR. All ASME Code Class 1, 2, and 3 components subject to inservice testing are shown on the drawings. To emphasize the Section XI Code Boundaries, P&ID pages containing lines other than ASME Code Piping have been omitted and non-ASME lines have been ghosted on the pages included. An explanation of the color coding system is provided at the end of the drawings.

' Regulatory Guide 1.26, "Quality Classifications and Standards for Water-Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants.

2 As allowed by Paragraphs IWB-1220, IWC-1220, IWC-1230, and Table INVD-2500-1 of Section XI.

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Pacific Gas and Electric Company Revision 0 77 Beale Street January 7, 2005 San Francisco, California 94177 INSERVICE TESTING OF PUMPS AND VALVES The pump and valve testing program demonstrates the operational readiness of Code Class 1, 2, and 3 pumps and valves which are required to perform a specific function in shutting down the reactor to the safe shutdown condition, in maintaining the safe shutdown condition or in mitigating the consequences of an accident. This program is presented in the attached Tables.

Table 1.0 (Pump IST Program) includes the pump name and number, the Code Class, applicable surveillance test procedure and test parameters, i.e., speed, differential pressure, discharge pressure, flow rate, pump bearings vibration, applicable relief request numbers, and remarks.

Table 1.1 contains all of the pump requests for relief from Code requirements.

Table 2.0 (Valve IST Program) includes the system name and number, valve number, description, P&ID coordinates, Code class, Code category, size, valve type (ball, butterfly, check, diaphragm, gate, globe, plug, or relief valve), actuator type (air operated, electric motor, electrohydraulic, manual, or solenoid-operated), normal valve position, test requirements, the test frequency, applicable stroke time and direction, relief request number (or cold shutdown or refueling outage justification numbers), procedure number, and remarks.

Table 2.1 contains all valve cold shutdown justifications per OM Code, ISTC-3521(c), and ISTC-3522(b).

Table 2.2 contains all valve refueling outage justifications per OM Code, ISTC-3521(e), ISTC-3522(c), and ISTC-522 1(c)(3).

Table 2.3 contains all of the valve requests for relief from Code requirements.

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Pacific Gas and Electric Company Revision 0 77 Beale Street January 7, 2005 San Francisco, California 94177 HOT STANDBY AS THE SAFE SHUTDOWN CONDITION OM Code, ISTA I1 00(a) defines the scope of the IST Program to include pumps and valves that are required to perform a specific function in shutting down a reactor to the safe shutdown condition, in maintaining the safe shutdown condition or in mitigating the consequences of an accident. Safe shutdown at Diablo Canyon Power Plant is defined as HOT STANDBY. DCPP SSER 7, page 3-3 and SSER 22, pages 93-95 indicate that DCPP is considered to be a Class 2 plant wherein a single suction line from RCS Hot Leg is considered acceptable since the plant has a safety related Auxiliary Feedwater system enabling decay heat removal for extended periods at Hot Standby. Technical Specification Bases B 3.3.4 states, "safe'shutdown condition is defined as MODE 3. With the unit in MODE 3, Auxiliary Feedwater (AFW) System and the Steam Generator (SG) safety valves can be used to remove core decay heat and meet all safety requirements."

Hence, DCPP is considered to be a Hot Standby plant.

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PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS TABLE 1.0 REV 0 (2005)

ASME OM Code 2001 (INCLUDING 2002 and 2003 ADDENDA) PAGE I OF 4 The attached sheets identify the pumps that are subject to the testing requirements of OM Code Subsection ISTB, and the requests for relief from code requirements.

LEGEND:

CODE CLASS ASME Code Class taken from DWG 102028 Revision 58 (104628 Rev. 47 for Unit 2), "ASME CODE BOUNDARIES FOR INSERVICE INSPECTION AND TESTING PROGRAM."

TEST FREQUENCY NOTATION Notation Frequency Q At least once per 92 days A At least once per 366 days 2Y At least once per 731 days NA Not applicable TEST PARAMETER NOTATION Notation Parameter N Pump Speed (if variable speed)

Dp Pump Differential Pressure Q Flow Rate V Pump Vibration P Pump Discharge Pressure 9B26YL00.DOC 40MIS 7

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ASME OM-Code 2001 (INCLUDING 2002 and 2003 ADDENDA) PAGE21OF4 P&ID CODE GROUP RELIEF REMARKS PUMP NAME AND NUMBER COORD CLASS ISTB-2000 REQUEST DEFINITION Safety Injection Pump I 57-E 2 B Safety Injection Pump 2 57-D 2 B Centrifugal Charging Pump 1 43D-C 2 A (44B-B)

Centrifugal Charging Pump 2 43D-D 2 A (44B-A)

Residual Heat Removal Pump 1 36-D 2 A (35-D)

Residual Heat Removal Pump 2 36-B 2 A (35-B)

Containment Spray Pump I 36-D 2 B Containment Spray Pump 2 36-A 2 B Auxiliary Feed Pump 2 (Mtr) 43-D 3 A Auxiliary Feed Pump 3 (Mtr) 43-D 3 A Auxiliary Feed Pump I (Turb) 43-C 3 B Auxiliary Saltwater Pump 1 311B-A 3 A RR2 Auxiliary Saltwater Pump 2 3 lB-C 3 A RR2 Component Cooling Water Pump I 50-D 3 A RRI Component Cooling Water Pump 2 52-D 3 A RRI Component Cooling Water Pump 3 54-D 3 A RRI Boric Acid Transfer Pump I 53B-E 2 A (57B-B)

Boric Acid Transfer Pump 2 53B-D 2 A (57B-A)

MU Watcr Transfer Pump 01 73-D 3 A MU Water Transfer Pump 02 76-D 3 A 9B26YL00.DOC 40MIS 8

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ASME OM-Code 2001 (INCLUDING 2002 and 2003 ADDENDA) PAGE 3 OF 4 ROUTINE QUARTERLY PUMP TESTS (GROUPS A & B)

PUMP NAME AND NUMBER RELIEF GROUP TEST PARAMETERS AND FREQUENCY REQUEST REMARKS PROCEDURE N Dp P Q V Safety Injection Pump I B P-SIP NA Q NA Q NA *Dp 2 1455 psid Safety Injection Pump 2 B P-SIP NA Q NA Q NA *Dp > 1455 psid Centrifugal Charging Pump I A P-CCP NA Q NA Q Q *Dp 2 2400 psid Centrifugal Charging Pump 2 A P-CCP NA Q NA Q Q *Dp 2 2400 psid Residual Heat Removal Pump I A P-RHR NA Q. NA Q Q *Dp 2 165 psid Residual Heat Removal Pump 2 A P-RHR NA Q NA Q Q *Dp 2 165 psid Containment Spray Pump I B P-CSP NA Q NA Q NA *Dp 2 205 psid Containment Spray Pump 2 B P-CSP NA Q NA Q NA *Dp > 205 psid Auxiliary Feed Pump 2 (Mtr) A P-AFW NA Q NA Q Q Auxiliary Feed Pump 3 (Mtr) A P-AFW NA Q NA Q Q Auxiliary Feed Pump I (Turb) B P-AFW Q Q NA Q NA Auxiliary Saltwater Pump I A P-ASW NA Q NA Q Q P-RR2 Auxiliary Saltwater Pump 2 A P-ASW NA Q NA Q Q P-RR2 Component Cooling Water Pump I A P-CCW NA Q NA Q Q P-RRI Component Cooling Water Pump 2 A P-CCW NA Q. NA Q Q P-RRI Component Cooling Water Pump 3 A P-CCW NA Q NA Q Q P-RRI Boric Acid Transfer Pump I A P-BAT NA Q NA Q Q Boric Acid Transfer Pump 2 A P-BAT NA Q NA Q Q MU Water Transfer Pump 01 A P-MUW NA Q NA Q Q MU Water Transfer Pump 02 A P-MUW NA Q NA Q Q

• Per Tech Spec Bases 9B26YL00.DOC 40MIS 9

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS TABLE 1.0 REV 0 (2005)

ASME OM-Code 2001 (INCLUDING 2002 and 2003 ADDENDA) PAGE 4 OF 4 COMPREHENSIVE PUMP TESTS (GROUPS A & B)

PUMP NAME AND NUMBER GROUP TEST PARAMETERS AND FREQUENCY RELIEF REMARKS PROCEDURE N Dp P Q V REQUEST Safety Injection Pump 1 B P-SIP-A NA 2Y NA 2Y 2Y Safety Injection Pump 2 B P-SIP-A NA 2Y NA 2Y 2Y Centrifugal Charging Pump I A P-CCP-A NA 2Y NA 2Y 2Y Centrifugal Charging Pump 2 A P-CCP-A NA 2Y NA 2Y 2Y Residual Heat Removal Pump I A P-RHR-A NA 2Y NA 2Y 2Y Residual Heat Removal Pump 2 A P-RHR-A NA 2Y NA 2Y 2Y Containment Spray Pump I B P-CSP-A NA 2Y NA 2Y 2Y Containment Spray Pump 2 B P-CSP-A NA 2Y NA 2Y 2Y Auxiliary Feed Pump 2 (Mtr) A P-AFW-A NA 2Y NA 2Y 2Y Auxiliary Feed Pump 3 (Mtr) A P-AFW-A NA 2Y NA 2Y 2Y Auxiliary Feed Pump I (Turb) B P-AFW-A 2Y 2Y NA 2Y 2Y Auxiliary Saltwater Pump I A P-ASW-A NA 2Y NA 2Y 2Y P-RR2 Auxiliary Saltwater Pump 2 A P-ASW-A NA 2Y NA 2Y 2Y P-RR2 Component Cooling Water Pump I A P-CCW-A NA 2Y NA 2Y 2Y P-RRI Component Cooling Water Pump 2 A P-CCW-A NA 2Y NA 2Y 2Y P-RRI Component Cooling Water Pump 3 A P-CCW-A NA 2Y NA 2Y 2Y P-RRI Boric Acid Transfer Pump I A P-BAT-A NA 2Y NA 2Y 2Y Boric Acid Transfer Pump 2 A P-BAT-A NA 2Y NA 2Y 2Y MU Water Transfer Pump 01 A P-MUW-A NA 2Y NA 2Y 2Y MU Water Transfer Pump 02 A P-MUW-A NA 2Y NA 2Y 2Y 9B26YL00.DOC 40MIS 10

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ASME OM-Code 2001 (INCLUDING 2002 AND 2003 ADDENDA) PAGE I OF 6 RELIEF REQUEST COMPONENT RELIEF REQUEST APPROVAL STATUS P-RR_ Component Cooling-Water Pumps P-RR2 Auxiliary Saltwater Pumps 9B26YL00.DOC 40MIS 11

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 1.1 ASME/ANSI OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 2 OF 6 NO. P-RRI System: Component Cooling Water Pumps: Pump Type Code Class: Group:

Component Cooling Water Pump 1-1 Centrifugal 3 A Component Cooling Water Pump 1-2 Centrifugal 3 A Component Cooling Water Pump 1-3 Centrifugal 3 A Component Cooling Water Pump 2-1 Centrifugal 3 A Component Cooling Water Pump 2-2 Centrifugal 3 A Component Cooling Water Pump 2-3 Centrifugal 3 A Functions:

The component cooling -vater (CCW) system removes heat from safety-related and nonsafety-related system components during normal operation and plant shutdown and transfers it to the ultimate heat sink via the auxiliary salt~water (ASW) system. The CCW pumps (CCWPs) are horizontally mounted centrifugal pumps.

The CCW system provides for safe shutdown and cooldown of the reactor by removing heat from safety-related and nonsafety-related system components after normal reactor shutdown, and from vital system components after an accident leading to an emergency shutdown.

Test Requirement ASME OM Code, subsection ISTB-5121(b) and ISTB-5123(b). The resistance of the system, shall be varied until flow rate equals the reference point.

Basis For Relief A variable flow measurement for the CCWP test is required because it is impractical to establish a fixed reference value(s). Relief is requested per IOCFR50.55a(f) (5) (iii). Diablo Canyon Power Plant (DCPP) had previously received relief for these pumps in the first and second 10 year plans.

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PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 1.1 ASME/ANSI OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 3 OF 6 NO. P-RR1(cont.)

The CCW system has varying heat loads, and therefore varying flow requirements. A full flow test line with a single throttle valve for the purpose of testing was not incorporated in the initial design of the system. For some plant conditions, a reference flow condition cannot be established without adversely affecting the system flow balance and Technical Specification (TS) operability requirements. Thus, these pumps must be tested in a manner that the CCW system remains properly flow balanced during and after the testing and each supplied load remains fully operable per TS to maintain the required level of plant safety during power operation. During refueling outages, CCW flow demand varies greatly due to reactor coolant system cooldown, clearing of components for maintenance, and spent fuel pool heat exchanger cooling water demand. Past experience at DCPP has shown that CCW flow during refueling outages is usually greater than flow during power operations and it is not practical to reduce flow in order to perform the CCWP IST.

At a minimum, perturbation of multiple systems is required to establish a-flow point due to the multiple flow paths of the CCW system. This abnormal configuration would have to be maintained for the length of time required to take vibration data and pump hydraulic data. In addition, the requirement for the Operators to manipulate valves required to adjust CCW flow to the reference point is adverse to ALARA.

Alternative Test Perform inservice tests on CCWPs using the following. A reference pump curve (flow rate vs. pump head) has been developed for each of the six CCWPs.

The following elements will be performed in developing the pump curves for testing the CCWPs. Existing data from previously performed inservice tests may be used in developing the curves. If a pump is replaced or repaired in such a way that inservice test parameters would require new reference values, then a preservice test performed per ISTB-5 100 would be used to develop the new reference pump curve and reference vibration values.

I. Pump reference curves will be developed when the pumps are known to be operating satisfactorily.

2. Instrumentation used to develop pump curves is at least as accurate (accuracy and range) as required by ASME OM Code Table ISTB-3400-1

3. Pump curves will be constructed using a minimum of five points.

4. Points used to construct the curves are beyond the flat portion (low flow rates) of the pump curve in a range, which includes the design bases flow rate.

5. Acceptance criteria for flow rate and differential pressure will be established by taking the more conservative of curves based on the limits of Table ISTB-5 100-1, or the operability criteria in TS or Safety Analysis Report.

6. Vibration levels will be measured over the range of pump conditions, and appropriate vibration acceptance criteria based on ISTB-5100-1, will be assigned for regions of the pump curve.

7. A new reference curve will be prepared by performing a preservice test procedure in accordance with ISTB-51 10, or the previous curve will be validated, if the pump curve is affected by replacement, repair, or routine service.

8. The comprehensive pump test will be performed at a flow that is +/-20% of design flow. Design flow for a CCW pump is 9200 gpm. The group A test will be performed at a flow rate that is at least 80% of design flow.

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REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 4 OF 6 NO. P-RRI(cont.)

References DCPP Final Safety Analysis Report Update Docket Numbers 50-275 and 50-323; Section 9.2.2 Component Cooling Water System.

DCPP Units I and 2 Technical Specification Bases for SR 3.6.6.3.

DCPP Supplemental Safety Evaluation Number 31, "Appendix A, Safety Evaluation Pump and Valve Inservice Testing Program," paragraph 2.3.3, "Relief Request (3)."

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PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN-PUMPS AND VALVES TABLE 1.1 ASME/ANSI OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 5 OF 6 NO. P-RR2 System: Auxiliary Saltwater Pumps: Pump Type Code Class: Group:

Auxiliary Saltwater Pump 1-1 Vertical Line Shaft 3 A Auxiliary Saltwater Pump 1-2 Vertical Line Shaft 3 A Auxiliary Saltwater Pump 2-1 Vertical Line Shaft 3 A Auxiliary Saltwater Pump 2-2 Vertical Line Shaft 3 A Functions:

The auxiliary saltwater (ASW) system supplies cooling water from the ultimate heat sink, the Pacific Ocean, to the component cooling water (CCW) heat exchangers. The CCW system, in turn, removes heat from nuclear primary plant equipment and components during normal plant operation, plant cooldowns, refueling and accident conditions, including a loss of coolant accident.

Each DCPP unit is provided with two redundant ASW trains. Each of these trains consist of a full capacity ASW pump (ASWP) and associated piping to supply the tube side of one of the CCW heat exchangers with cooling water. Each pump may also be cross-connected so as to supply the opposite train heat exchanger.

Test Requirement ASME OM Code, subsection ISTB-5221(b) and ISTB-5223(b). The resistance of the system, shall be varied until flow rate equals the reference point.

Basis For Relief Adjustment to a specific reference value for the ASWP test is not practical because the pump flow rate varies based on tide level (suction pressure) and heat exchanger differential pressure (system resistance),

which cannot be readily controlled. The CCW heat exchanger outlet throttle valves are the only valves which can be adjusted to set ASWP flow at the desired test flow. These valves are sealed in a throttled position which ensures the train can perform its required safety function under worst case conditions. A CCW heat exchanger is considered inoperable after its outlet valve is adjusted until a flow verification test is performed. The flow verification test requires that the system alignment with the most system resistance i.e.,

ASW pump #I to CCW heat exchanger #2 (or ASW pump #2 to CCW heat exchanger #1) be used. This realignment, test and subsequent data analysis takes several hours, during which time the CCW heat exchanger is inoperable. Diablo Canyon Technical Specifications require that the second vital CCW heat exchanger be placed in service whenever ultimate heat sink temperature is greater than 641F. In order to meet the Technical Specification LCO, ASW pump tests performed when ultimate heat sink temperatures are above 641F must be performed with two CCW heat exchangers in service and result in test flows of up to 14,000 gpm. When the test is run with only one CCW heat exchanger in service (normal test alignment),

reference pump flow is between 11,500 and 12,500 gpm. Relief is requested per 10CFR50.55a(f) (5) (iii).

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REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 6 OF 6 NO. P-RR2(cont.)

Alternative Test Perform inservice tests on ASWPs using the following. A reference pump curve (flow rate vs. pump head) has been developed for each of the four ASWPs.

The following elements will be performed in developing the pump curves for testing the ASWPs:

1. Pump reference curves will be developed when the pumps are known to be operating satisfactorily.

2. Instrumentation used to develop pump curves is at least as accurate (accuracy and range) as required by ISTB-3500-1.

3. These pump curves will be constructed using a minimum of five points.

4. Points used to construct the curves are beyond the flat portion (low flow rates) of the pump curve in a range which includes the design bases flow rate.

5. Acceptance criteria for flow rate and differential pressure will be established by taking the more conservative of curves based on the limits of Table ISTB-5200-1, or the operability criteria in TS or Safety Analysis Report.

6. Vibration levels will be measured over the range of pump conditions, and appropriate vibration acceptance criteria based on Table ISTB-5200-1, will be assigned for regions of the pump curve.

7. A new reference curve will be prepared, or the previous curve will be validated, if the pump curve is affected by replacement, repair, or routine service.

8. The comprehensive pump test will be performed at a flow rate that is +/-20% of design flow. The group A test will be performed at a flow that is at least 80% of design flow. Design flow for the ASW pumps is 11,000 gpm.

References DCPP Final Safety Analysis Report Update Docket Numbers 50-275 and 50-323; Section 9.2.2 Component Cooling Water System.

DCPP Units I and 2 Technical Specification 3.7.8.

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ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE I OF 52 The attached sheets identify the system valves that are subject to the testing requirements of ASME OM Code Subsection ISTC, and the requests for relief from code requirements.

LEGEND:

VALVE CLASS (VLV CLS)

ASME code class taken from DWG 102028 Revision 58 (104628 Rev. 47 for Unit 2) "ASME CODE BOUNDARIES FOR INSERVICE INSPECTION AND TESTING PROGRAM."

NOTE: TS indicates a non ASME code class valve that is required to be tested by Technical Specification.

ISTC indicates a non ASME code class valve that is required to be tested in accordance with ASME OM Code, Subsection ISTC.

VALVE CATEGORY (VLV CAT)

ISTC-1300 VALVE CATEGORIES and ISTC-51 10 for Power Operated Relief Valves (category 'P')

VALVE SIZE (VLV SIZ)

ASME SIZE IN INCHES VALVE TYPE (VLV TYP) NOTATION NOTATION TYPE BA Ball Valve BV Butterfly Valve CK Check Valve DI Diaphragm Valve GA Gate Valve GL Globe Valve PL Plug Valve RV Relief Valve

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• ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 2 OF 52

. LEGEND: (Continued)

ACTUATOR TYPE (ACT TYP) NOTATION NOTATION TYPE A Air Operated E Electric Motor H Electrohydraulic M Manual N None S Solenoid Operated NORMAL POSITION (NRM POS) NOTATION NOTATION POSITION 0 Open C Closed LO Locked, Sealed, or De-energized (Breaker Open) Open LC Locked, Sealed, or De-energized (Breaker Open) Closed V Variable 9B26YL00.DOC 40MIS 18

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2603 ADDENDA) PAGE 3 OF 52 LEGEND: (Continued)

TEST REQUIREMENT (TEST REQ) NOTATION NOTATION REQUIREMENT CM Check Valve Condition Monitoring Test EC Exercise of Check Valve - Full Stroke EP Exercise of Check Valve or Valve - Partial Stroke EF Exercise of Valve - Full Stroke EM Manual Exercise of Check Valve/Disassembly Inspection EN Nonintrusive Exercise of Check Valve LT Valve Leak Test Pi Position Indication Test RT Test Per ASME OM Code Mandatory Appendix I for Pressure Relief Devices NOTE: Valve Fail Safe testing is required by ISTC-3560. Valves with Fail Safe actuators are tested by the full stroke tests of the valves. A specific Test Requirement was not created for Fail Safe tests.

TEST FREQUENCY (TEST FRQ) NOTATION NOTATION FREQUENCY Q At least once per 92 days.

CS At least each cold shutdown but not more frequently than once per 92 days.

(This notation identifies valves that cannot be exercised during plant operation. A statement of the technical justification for not full stroke exercising these valves during plant operation is included in Table 2.1).

R At least once per each refueling interval.

(This notation identifies valves that cannot be exercised during plant operation nor full stroke exercised during cold shutdown. A statement of the technical justification for not full stroke exercising these valves during plant operation and whether they will be part stroked or not tested at all during cold shutdown is included in Table 2.2).

2Y At least once per 731 days.

T Per ASME OM Code Mandatory Appendix I for Pressure Relief Devices RR Tested on a rotational basis during refueling outages.

J Per I0CFR50 Appendix J, Option B.

S At least once per 184 days CMP Per ASME OM Code Mandatory Appendix II for Check Valve Condition Monitoring Program 9B26YL00.DOC 40MIS 19

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 4 OF 52 LEGEND: (Continued)

STROKE TIME (STR TIM)

For power operated valves, the maximum allowed stroke time is given in seconds followed by a "c" for closing, or an "o" for opening, or an "o/c" for both opening and closing. For manual valves and check valves, this column denotes that the valve has a safety function in the "c" closed position, in the "o" open position, or in both the "o/c" open and closed position.

RELIEF REQUEST (REL REQ)

Numbers in this column refer to either a cold shutdown justification (CS), a refueling outage justification (RO), or a relief request (RR). These justifications and relief requests are found in TABLES 2.1, 2.2, and 2.3 respectively.

PROCEDURE NUMBER (PROC NO.)

Identifies procedure used to meet test requirement. If valve is stroked routinely during normal operations, then NORM OP.

REMARKS The numbers in the remarks column refer to the list of remarks on the last page of TABLE 2.0.

DRAWING REFERENCE NUMBERS UNIT 1: 1020--series UNIT 2: 1080--series UNIT 2 SPECIFIC INFORMATION INDICATED BY PARENTHESES 9B26YL00.DOC 40MIS 20

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT -UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 5 OF 52 FEEDWATER SYSTEM P& ID NO. 1020 03 VALVE VALVE P &ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FW-348 AUX FP-1 SUCT CK FROM CST 42-C 3 C 8 CK N C CM CMP 0/c V-18 FW-349 AUX FP-2 SUCT CK FROM RWS 41-C 3 C 8 CK N C CM CMP o/c V-18 FW-350 AUX FP-2 SUCT CK FROM CST 42-D 3 C 6 CK N C CM CMP 0/c V-18E FW-352 AUX FP-3 SUCT CK FROM CST 42-D 3 C 6 CK N C CM CMP 0/c V-18E FW-353 AUX FP-2&3 SUCT CK FROM RWS 41-D 3 C 8 CK N C CM CMP olc V-18 FW-354 AUX FP-2 RECIRC CK 43-C 3 C 1.5 CK N C CM CMP 0/c V-18E FW-355 AUX FP-2 RECIRC CK 43-D 3 C 1.5 CK N C CM CMP 0/c V-18E FW-356 AUX FP-3 RECIRC CK 44-D 3 C 1.5 CK N C CM CMP o/c V-18E FW-361 AUX FP-2 DISCH CK 44-C 3 C 6 CK N C CM CMP o/c V-18 FW-362 AUX FP-2 DISCH CK 44-D 3 C 4 CK N C CM CMP o/c V-18E FW-363 AUX FP-3 DISCH CK 44-D 3 C 4 CK N C CM CMP o/c V-18E FW-367 SG-2 FW CK 47-A 2 A,C 16 CK N O EC CS C CS I V-3P3 EC CS 0 #1 LT 2Y C V-26 #2-ADMIN Tested R FW-368 SG-1 FW CK 47-A 2 A,C 16 CK N O EC CS C CS I V-3P3 EC CS 0 #l LT 2Y C V-26 #2-ADMIN Tested R 9B26YL00.DOC 40MIS 21

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 6 OF 52 FEEDWATER SYSTEM P& ID NO. 1020 03 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FW-369 AUX FP-I TO SG-1 CK 47-C 2 C 3 CK N C EC CS o/c CS2 P-AFW FW-370 AUX FP-2 TO SG-I CK 47-D 2 C 3 CK N C EC CS o/c CS2 P-AFW FW-371 AUX FP-I TO SG-2 CK 47-C 2 C 3 CK N C EC CS o/c CS2 P-AFW FW-372 AUX FP-2 TO SG-2 CK 47-D 2 C 3 CK N C EC CS o/c CS2 P-AFW FW-373 AUX FP-1 TO SG-3 CK 47-B 2 C 3 CK N C EC CS o/c CS2 P-AFW FW-374 AUX FP-3 TO SG-3 CK 47-C 2 C 3 CK N C EC CS o/c CS2 P-AFW FW-375 AUX FP-t TO SG-4 CK 47-B 2 C 3 CK N C EC CS o/c CS2 P-AFW FW-376 AUX FP-3 TO SG-4 CK 47-C 2 C 3 CK N C EC CS o/c CS2 P-AFW FW-377 SG-1 AUX FW 1ST CK 49-B 2 C 3 CK N C CM CMP o/c V-18F FW-378 SG-2 AUX FW 1ST CK 48-B 2 C 3 CK N C CM CMP o/c V-18F FW-379 SG-3 AUX FW 1ST CK 48-B 2 C 3 CK N C CM CMP o/c V-18F FW-380 SG-4 AUX FW 1ST CK 48-B 2 C 3 CK N C CM CMP o/c V-18F 9B26YL00.DOC 40MIS 22

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 7 OF 52 FEEDWATER SYSTEM P& ID NO. 1020 03 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FW-531 SG-3 FW CK 47-A 2 A,C 16 CK N 0 EC CS c CS! V-3P3 EC CS o #1 LT 2Y c V-26 #2-ADMIN Tested R FW-532 SG-4 FW CK 47-A 2 A,C 16 CK N 0 EC CS c CS! V-3P3 EC CS o #1 LT 2Y c V-26 #2-ADMIN Tested R FCV-436 RWS SUP AUX FP-I 41-C 3 B 8 BV M C EF Q* o/c V-3P4 *Per Tech Spec FCV-437 RWS SUP AUX FP-2 & 3 41-D 3 B 8 BV M C EF Q* o/c V-3P4 *Per Tech Spec FCV-438 SG-1 FW ISO 48-A 2 B 16 GA E 0 PI 2Y NA V-2UIC EF CS 60c CS1 V-3P2 FCV-439 SG-2 FW ISO 47-A 2 B 16 GA E 0 PI 2Y NA V-2U2C EF CS 60c CSI V-3P2 FCV-440 SG-3 FW ISO 47-A 2 B 16 GA E 0 P1 2Y NA V-2U3C EF CS 60c CSI V-3P2 FCV-441 SG-4 FW ISO 48-A 2 B 16 GA E 0 PI 2Y NA V-2U4C EF CS 60c CS! V-3P2 LCV-106 AUX FP-I TO SG-1 REG 47-C 2 B 3 GL E 0 PI 2Y NA V-2UID EF Q 20o/c V-3P5 LCV-107 AUX FP-1 TO SG-2 REG 47-C 2 B 3 GL E 0 PI 2Y NA V-2U2D EF Q 20o/c V-3P5 LCV-108 AUX FP-1 TO SG-3 REG 47-B 2 B 3 GL E 0 P1 2Y NA V-2U3D EF Q 200/c V-3P5 LCV-109 AUX FP-1 TO SG-4 REG 47-B 2 B 3 GL E 0 PI 2Y NA V-2U4D EF Q 20o/c V-3P5 LCV-I 10 AUX FP-2 TO SG-I REG 47-D 2 B 2 GL H 0 PI 2Y NA V-2UID EF Q 40o/c V-3P6A LCV- 11I AUX FP-2 TO SG-2 REG 47-D 2 B 2 GL H 0 PI 2Y NA V-2U2D EF Q 40o/c V-3P6A 9B26YL00.DOC 40MIS 23

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2

INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 8 OF 52 FEEDWATER SYSTEM P& ID NO. 1020 03 VALVE VALVE VALVE P&ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS LCV-1 13 AUX FP-3 TO SG-4 REG 47-C 2 B 2 GL H 0 Pl 2Y NA V-2U4D EF Q 40o/c V-3P6B LCV-1 15 AUX FP-3 TO SG-3 REG 47-C 2 B 2 GL H 0 P1 2Y NA V-2U3D EF Q 40o/c V-3P6B FCV-5 10 SG-I FW REG 33A-E -TS B 12 GL A 0 EF CS* 7c V-3PI *Per Tech Spec (38-C) Pl 2Y NA V-2UIC FCV-520 SG-2 FW REG 33A-D TS B 12 GL A 0 EF CS* 7c V-3PI *Per Tech Spec (38-D) Pl 2Y NA V-2U2C FCV-530 SG-3 FW REG 33A-A TS B 12 GL A 0 EF CS* 7c V-3PI *Per Tech Spec (38-E) Pl 2Y NA V-2U3C FCV-540 SG-4 FW REG 33A-C TS B 12 GL A 0 EF CS* 7c V-3PI *Per Tech Spec (38-D) Pl 2Y NA V-2U4C FCV-1510 SG-1 FW REG BYPASS 33A-D TS B 6 GL A C EF CS* 7c V-3PI *Per Tech Spec (37-B) Pl 2Y NA V-2UIC FCV-1520 SG-2 FW REG BYPASS 33A-C TS B 6 GL A C EF CS* 7c V-3PI *Per Tech Spec (38-D) Pl 2Y NA V-2U2C FCV-1530 SG-3 FW REG BYPASS 33A-A TS B 6 GL A C EF CS* 7c V-3PI *Per Tech Spec (38-E) Pl 2Y NA V-2U3C FCV-1540 SG-4 FW REG BYPASS 33A-B TS B 6 GL A C EF CS* 7c V-3PI *Per Tech Spec (38-E) Pl 2Y NA V-2U4C RV-536 AUX FP-I SUCT RELIEF 42-C 3 C Ix1.5 RV N C RT T NA M-77 I 00#

(42-D)

RV-537 AUX FP-2&3 SUCT RELIEF 41-D 3 C IlI.5 RV N C RT T NA M-77 100#

9B26YL00.DOC 40MIS 24

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 9 OF 52 TURBINE STEAM SYSTEM P& ID NO. 1020 04 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS MS-1015 SG-l 10% STM DUMP ISO VALVE 31-A 2 B 8 GA M 0 EF 2Y NA V-3RI MS-1068 SG-I MS LINE CK 31-A ISTC C 28 CK N 0 EM RR o/c ROI V-18 MS-2015 SG-2 10% STM DUMP ISO VALVE 30-C 2 B 8 GA M 0 EF 2Y NA V-3RI MS-2066 SG-2 MS LINE CK 31-B ISTC C 28 CK N 0 EM RR o/c ROI V-18 MS-3015 SG-3 10% STM DUMP ISO VALVE 31-D 2 B 8 GA M 0 EF 2Y NA V-3RI MS-3062 SG-3 MS LINE CK 31-D ISTC C 28 CK N 0 EM RR o/c ROI V-18 MS-4015 SG-4 10% STM DUMP ISO VALVE 31-E 2 B 8 GA M 0 EF 2Y NA V-3RI MS-4062 SG-4 MS LINE CK 31-E ISTC C 28 CK N 0 EM RR o/c ROI V-18 MS-5166 SG-2 STM TO AUX FP-I CK 30-B 2 C 4 CK N C EM RR o/c R02 V-18 MS-5167 SG-3 STM TO AUX FP-I CK 31-C 2 C 4 CK N C EM RR o/c R02 V-18 FCV-22 SG-4 MSIV BYPASS 31-E 2 B 3 GL A C Pi 2Y NA V-2U4A EF Q 5c V-3R4 FCV-23 SG-3 MSIV BYPASS 31-C 2 B 3 GL A C Pi 2Y NA V-2U3A EF Q Sc V-3R4 FCV-24 SG-2 MSIV BYPASS 31-B 2 B 3 GL A C Pi 2Y NA V-2U2A EF Q 5c V-3R4 FCV-25 SG-I MSIV BYPASS 31-A 2 B 3 GL A C Pi 2Y NA V-2UIA EF Q Sc V-3R4 9B26YL00.DOC 40MIS 25

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 10 OF 52 TURBINE STEAM SYSTEM P& ID NO. 1020 04 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FCV-37 SG-2 STM TO AUX FP-1 30-B 2 B 4 GA E 0 Pi 2Y NA V-2U2E EF Q 30o/c V-3R6 FCV-38 SG-3 STM TO AUX FP-I 31-C 2 B 4 GA E 0 Pi 2Y NA V-2U3E EF Q 30o/c V-3R6 FCV41 SG-I MSIV 31-A 2 B 28 CK A 0 Pi 2Y NA V-2UIA EF CS Sc CS3 V-3R2 EF CS 0 CS3 V-3R2 FCV-42 SG-2 MSIV 31-B 2 B 28 CK A 0 Pi 2Y NA V-2U2A EF CS Sc CS3 V-3R2 EF CS 0 CS3 V-3R2 FCV-43 SG-3 MSIV 31-D 2 B 28 CK A 0 PI 2Y NA V-2U3A EF CS Sc CS3 V-3R2 EF CS 0 CS3 V-3R2 FCV-44 SG-4 MSIV 31-E 2 B 28 CK A 0 PI 2Y NA V-2U4A EF CS Sc CS3 V-3R2 EF CS 0 CS3 V-3R2 FCV-95 AUX FP-1 STM SUP 31-B 2 B 4 GA E C PI 2Y NA V-2U5B EF Q 30o V-3R5 FCV-I51 SG-I BD ISOL OC 72-C 2 B 3 GA A 0 Pi 2Y NA V-2J4 EF Q lOc V-3S2 FCV-154 SG-2 BD ISOL OC 72-C 2 B 3 GA A 0 PI 2Y NA V-2J4 (72-D) EF Q lOc V-3S2 9B26YL00.DOC 40MIS 26

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 11 OF 52 TURBINE STEAM SYSTEM P& ID NO. 1020 04 VALVE VALVE P&ID V'LV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD C:LS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FCV-157 SG-3 BD ISOL OC 72-D 2 B 3 GA A 0 PI 2Y NA V-2J4 EF Q lOc V-3S2 FCV-160 SG-4 BD ISOL OC 72-E 2 B 3 GA A 0 PI 2Y NA V-2J4 EF Q lOc V-3S2 FCV-244 SG-4 SAMPLE ISOL OC 72-E 2 B .75 GL A 0 PI 2Y NA V-2J4 EF Q lOc V-3S2 FCV-246 SG-3 SAMPLE ISOL OC 72-D 2 B .i5 GL A 0 Pi 2Y NA V-2J4 EF Q 10c V-3S2 FCV-248 SG-2 SAMPLE ISOL OC 72-C 2 B .75 GL A 0 PI 2Y NA V-2J4 EF Q lOc V-3S2 FCV-250 SG-1 SAMPLE ISOL OC 72-C 2 B .75 GL A 0 PI 2Y NA V-2J4 EF Q lOc V-3S2 FCV-760 SG-I BD ISOL IC 71-C 2 B 3 GL A 0 PI 2Y NA V-2NI (70-C) EF Q Sc V-3R3 FCV-761 SG-2 BD ISOL IC 71-C 2 B 3 GL A 0 Pi 2Y NA V-2NI (70-D) EF Q Sc V-3R3 FCV-762 SG-3 BD ISOL IC 71-D 2 B 3 GL A 0 PI 2Y NA V-2NI (70-D) EF Q Sc V-3R3 FCV-763 SG-4 BD ISOL IC 71-E 2 B 3 GL A 0 Pi 2Y NA V-2N I (70-E) EF Q Sc V-3R3 PCV-19 SG-1 10% ATM DUMP 30-A 2 B, P 8 GL A C Pi R NA V-2UIB EF R 20o/40c V-3RI LT R NA V-3RI APPX I TABLE I-8220-1 9B26YL00.DOC 40MIS 27

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 12 OF 52 TURBINE STEAM SYSTEM P& ID NO. 1020 04 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TS STR REL PROC T

NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FR TIM REQ NO. REMARKS Q

PCV-20 SG-2 10% ATM DUMP 30-C 2 B, P 8 GL A C PI R NA V-2U2B EF R 20o/40c V-3RI LT R NA V-3RI APPX I TABLE I-8220-1 PCV-21 SG-3 10% ATM DUMP 31-D 2 B, P 8 GL A C Pi R NA V-2U3B EF R 20o/40c V-3R1 LT R NA V-3RI APPX I TABLE I-8220-1 PCV-22 SG-4 10% ATM DUMP 31-E 2 B,P 8 GL A C Pi R NA V-2U4B EF R 20o/40c V-3RI LT R NA V-3R1 APPX I TABLE I-8220-1 RV-3 SG-1 SAFETY 30-A 2 C 6 RV N C RT T NA M-77 1065#

RV-4 SG-1 SAFETY 31-A 2 C 6 RV N C RT T NA M-77 1078#

RV-5 SG-I SAFETY 31-A 2 C 6 RV N C RT T NA M-77 1090#

RV-6 SG-I SAFETY 31-A 2 C 6 RV N C RT T NA M-77 1103#

RV-7 SG-2 SAFETY 30-C 2 C 6 RV N C RT T NA M-77 1065#

RV-8 SG-2 SAFETY 31-C 2 C 6 RV N C RT T NA M-77 1078#

RV-9 SG-2 SAFETY 31-C 2 C 6 RV N C RT T NA M-77 1090#

RV-10 SG-2 SAFETY 31-C 2 C 6 RV N C RT T NA M-77 1103#

9B26YL00.DOC 40MIS 28

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 13 OF 52 TURBINE STEAM SYSTEM P& ID NO. 1020 04 VALVE VALVE P&ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS RV-II SG-3 SAFETY 31-D 2 C 6 RV N C RT T NA M-77 1065#

RV-12. SG-3 SAFETY 31-D 2 C 6 RV N C RT T NA M-77 1078#

RV-13 SG-3 SAFETY 32-D 2 C 6 RV N C RT T NA M-77 1090#

RV-14 SG-3 SAFETY 31-D 2 C 6 RV N C RT T NA M-77 1103#

RV-58 SG-4 SAFETY 31-E 2 C 6 RV N C RT T NA M-77 1065#

RV-59 SG-4 SAFETY 31-E 2 C 6 RV N C RT T NA M-77 1078#

RV-60 SG-4 SAFETY 32-E 2 C 6 RV N C RT T NA M-77 1090#

RV-61 SG-4 SAFETY 31-E 2 C 6 RV N C RT T NA M-77 1103#

RV-222 SG-I SAFETY 31-A 2 C .6 RV N C RT T NA M-77 1115#

RV-223 SG-2 SAFETY 31-C 2 C 6 RV N C RT T NA M-77 1115#

RV-224 SG-3 SAFETY 31-D 2 C 6 RV N C RT T NA M-77 1115#

RV-225 SG-4 SAFETY 31-E 2 C 6 RV N C RT T NA M-77 1115#

9B26YL00.DOC 40MIS 29

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 14 OF 52 AUXILIARY STEAM SYSTEM P& ID NO. 1020 06 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS AXS-208 AXS STM SUP TO CONT ISO IC 43-E 2 A 2 CK N C LT J c V-670 Tested R EC R o R03 V-670 EC R c R03 V-670 AXS-26 AUX STM SUP TO CONT ISO OC 43-D 2 A 2 GA M LC LT J c V-670 PASSIVE Tested R 9B26YL00.DOC 40MIS 30

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV O (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 15 OF 52 REACTOR COOLANT SYSTEM P& ID NO. 1020 07 VALVE VALVE P &ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS RCS-508 RV & STM LK OFF HDR TO PRT 44-E 3 C 4 CK N C CM CMP o/c V-18 RV function RCS-512 MISC EQUIP DR TANK ISOL OC 48-A 2 A 3/4 GL M LC LT J C V-671 PASSIVE PCV-455C PZR PORV 40-C I B,P 2 GL A C Pi R NA V-2TI EF R 2.9o V-3J2 LT R NA V-2TI APP I TAB 1-8220-1 PCV-456 PZR PORV 40-B I B,P 2 GL A C PI R NA V-2TI EF R 2.9o V-3J2 LT R NA V-2TI APP I TAB 1-8220-1 PCV-474 PZR PORV 40-C I B, P 2 GL A C PI R NA V-2TI EF R 2.9o V-3J2 LT R NA V-2TI APP I TAB 1-8220-1 8000A PZR PORV ISOL 41-C I B 3 GA E 0 Pi 2Y NA V-2TI EF Q 20c V-3JIA 8000B PZR PORV ISOL 41-C I B 3 GA E O Pi 2Y NA V-2TI EF Q 20c V-3JIB 8000C PZR PORV ISOL 40-B I B 3 GA E 0 Pi 2Y NA V-2TI EF Q 20c V-3JIC 801 OA PZR SAFETY 43-D I A,C 6 RV N C RT T NA M-77 2485#

8010B PZR SAFETY 42-D I A,C 6 RV N C RT T NA M-77 2485#

8010C PZR SAFETY 42-D I A,C 6 RV N C RT T NA M-77 2485#

8028 RV DISC HDR TO PRT ISOL IC 47-C 2 A,C 4 CK N C LT J c V-671 CM CMP o/c V-18 RV function 8029 PRI WTR TO PRT ISOL OC 48-D 2 A 3 BA A 0 Pi 2Y NA V-2J7 LT J c V-652A Tested R EF Q 1Oc V-3S7 9B26YL00.DOC 40MIS 31

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 16 OF 52 REACTOR COOLANT SYSTEM P& ID NO. 1020 07 VALVE . VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8034A PRT TO GA ISOL IC 48-E 2 A 3/8 GL A 0 Pi 2Y NA V-204 LT i c V-676B EF Q lOc V-3S8 8034B PRT TO GA ISOL OC 48-E 2 A 3/8 GL A C Pi 2Y NA V-2J7 LT i c V-676B EF Q lOc V-3S8

• 8045 N2 TO PRT ISOL OC 48-E 2 A 3/4 DI A 0 Pi 2Y NA V-2J7 LT i c V-652B Tested R EF Q lOc V-3S8 8046 PRI WTR TO PRT ISOL IC 48-D 2 A,C 3 .CK N C LT i c V-652A EC R c R03 V-652A EC R 0 R03 #1 8047 N2 TO PRT ISOL IC 48-E 2 A,C 3/4 CK N C LT J c V-652B Tested R EC R 0 R03 #1 EC R c R03 8078A REACTOR VESSEL 75-A 2 B I GL S LC Pi 2Y NA V-2T2 Tested R HEAD VENT EF R 2o R04 V-2T2 8078B REACTOR VESSEL 75-B 2 B 1 GL S LC Pi 2Y NA V-2T2 Tested R HEAD VENT (75-A) EF R 2o R04 V-2T2 8078C REACTOR VESSEL 75-B 2 B 1 GL S LC Pi 2Y NA V-2T2 Tested R HEAD VENT (75-A) EF R 2o R04 V-2T2 8078D REACTOR VESSEL 75-A 2 B I GL S LC PI 2Y NA V-2T2 Tested R HEAD VENT EF R 2o R04 V-2T2 9B26YL00.DOC 40MIS 32

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 17 OF 52 CHEMICAL AND VOLUME CONTROL SYSTEM P& ID NO. 1020 08 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FCV-1 l OA BA SUP TO BLENDER 41C-C 2 B 2 GL A C P1 2Y NA V-2K (40B-B) EF Q 1Oo V-3EI #3 - Hosgri LCV-1 12B VCT OUT ISOL 46B-C ISTC B 4 GA E 0 Pi 2Y NA V-211 (43B-D) EF CS 10c CS4 V-3K12 LCV-1 12C VCT OUT ISOL 47B-C ISTC B 4 GA E 0 PI 2Y NA V-211 (43B-D) EF CS 10c CS4 V-3K12 8100 RCP SEAL WTR RETRN ISOL OC 38C-A 2 A 4 GA E O Pi 2Y NA V-211 (39-E) LT 3 c V-645 Tested R EF CS 10c C55 V-3K2 RRI 8104 EMERG BORATE 44C-C 2 B 2 GL E C Pi 2Y NA V-2K (41 B-B) EF Q lOo V-3E5 8105 CENT CHG PP RECIRC 43B-E ISTC B 2 GL E 0 Pi 2Y NA V-211 (41B-A) EF CS 10c CS6 V-3K9 8106 CENT CHG PP RECIRC 43B-E 2 B 2 GL E 0 Pi 2Y NA V-211 (41B-A) EF CS 10c CS6 V-3K9 8107 CHG LINE ISOL OC 49D-B 2 B 3 GA E 0 Pi 2Y NA V-211 (47B-C) EF CS 14c CS7 V-3K13 8108 CHG LINE ISOL 48D-B 2 B 3 GA E 0 Pi 2Y NA V-211 (46B-C) I EF CS 14c CS7 V-3K13 8109 RCP SEAL WTR RETRN ISOL IC 37C-A 2 A,C 3/4 CK N 0 LT J c V-645 Tested R (38-D) EC R o/c RO5 V-645 9B26YL00.DOC 40MIS 33

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 18OF52 CHEMICAL AND VOLUME CONTROL SYSTEM P& ID NO. 1020 08 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8112 RCP SEAL WTR RETRN ISOL IC 37C-A 2 A 4 GA E O PI 2Y NA V-211 (38-E) LT J c V-645 Tested R EF CS 10c CS5 V-3K2 RRI 8145 PZR AUX SPRAY 43-B I B 2 GL A C PI 2Y NA V-2S (43-D) EF CS 10o CS8 V-3K8 8146 NORMAL CHG 43-B 2 B 2 GL A O PI 2Y NA V-2S (43-D) EF CS 20o CS9 V-3K5 8147 ALTERNATE CHG 42-B 2 B 2 GL A C PI 2Y NA V-2S (42-D) EF CS 20o CS9 V-3K5 8148 PZR AUX SPRAY BYP 43-B I B 2 GL A C PI 2Y NA V-2S (43-D) EF CS 10O CS8 V-3K8 8149A LTDN ORF RO-27 ISOL IC 43-C 2 A 2 GL A C PI 2Y NA V-2Y LT i c V-635 EF CS 10c CS10 V-3K7A 9B26YL00.DOC 40MIS 34

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON P>OWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 19 OF 52 CHEMICAL AND VOLUME CONTROL SYSTEM P& ID NO. 1020 08 VALVE VALVE P &ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8149B LTDN ORF RO-27 ISOL IC 43-C 2 A 2 GL A 0 PI 2Y NA V-2Y LT J c V-635 EF CS 1Oc CS10 V-3K7A 8149C LTDN ORF RO-27 ISOL IC 43-C 2 A 2 GL A C Pi 2Y NA V-2Y LT J c V-635 EF CS 1Oc CS10 V-3K7A 8152 LTDN LINE ISOL OC 44-C 2 A 2 GL A 0 PI 2Y NA V-218 LT J c V-635 EF CS 1Oc CSI I V-3K7B 8367A RCP-1 SEAL INJ 2ND CK IC 34-D I C 2 CK N 0 EC R 0 R06 (31-C) EC R c R06 V-18N 8367B RCP-2 SEAL INJ 2ND CK IC 34A-D I C 2 CK N 0 EC R 0 R06 (33-C) EC R c R06 V-18N 8367C RCP-3 SEAL INJ 2ND CK IC 34B-D I C 2 CK N 0 EC R 0 R06 #1 (35-C) EC R c R06 V-18N 8367D RCP-4 SEAL INJ 2ND CK IC 34C-D I C 2 CK N 0 EC R 0 R06 #1 (37-C) EC R c R06 V-18N 8368A - RCP-1 SEAL INJ IST CK IC 31-D 2 A,C 2 CK N 0 LT J c V-641 Tested R (31-B) EC R c R03 V-641 EC R 0 R03 #1 8368B RCP-2 SEAL INJ I ST CK IC 31A-D 2 A,C 2 CK N 0 LT J c V-641 Tested R (33-B) EC R c R03 V-641 EC R 0 R03 #l 8368C RCP-3 SEAL INJ I ST CK IC 31B-D 2 A,C 2 CK N O LT J c V-641 Tested R (35-B) EC R c R03 V-641 EC R 0 R03 #1 8368D RCP-4 SEAL INJ IST CK IC 31C-D 2 A,C 2 CK N 0 LT J c V-641 Tested R (37-B) EC R c R03 V-641 EC R 0 R03 #1 9B26YL00.DOC 40MIS 35

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 20 OF 52 CHEMICAL AND VOLUME CONTROL SYSTEM P& ID NO. 1020 08 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8372A RCP-1 SEAL INJ 3RD CK IC 33-D I C 2 CK N O EC R o R06 #1 (31-C) EC R c R06 V-18N 8372B RCP-2 SEAL INJ 3RD CK IC 33A-D I C 2 CK N O EC R o R06 #1 (33-C) EC R c R06 V-18N 8372C RCP-3 SEAL INJ 3RD CK IC 33B-D I C 2 CK N O EC R o R06 #1 (35-C) EC R c R06 V-18N 8372D RCP-4 SEAL INJ 3RD CK IC 33C-D I C 2 CK N O EC R o R06 #1 (37-C) EC R c R06 V-18N 8377 PZR AUX SPRAY CK 42-A I C 2 CK N C EC R o R07 V-3K8 (42-E) EC R c R07 V-1 8P 8378A CHG TO LOOP 3 COLD LEG CK 41-B I C 3 CK N O EC R o R08 V-3K5 (41-E) EC R c RO8 V-S8P 8378B CHG TO LOOP 4 COLD LEG CK 41-A I ,C 3 CK N O EC R o RO8 V-3K5 (41-E) EC R c RO8 V-18P 8378C CHG LINE CK 43-D 2 C 3 CK N O EC R o RO8 V-3K5 (43-B) EC R c RO8 V-18P 8379A CHG TO LOOP 3 COLD LEG CK 41-B I C 3 CK N O EC R o RO8 V-3K5 (41-E) EC R c RO8 V-S8P 8379B CHG TO LOOP 4 COLD LEG CK 41-A I C 3 CK N O EC R o R08 V-3K5 (41 -E) EC R c R08 V-18P 8440 VCT OUTLET CK 48B-C 2 C 4 CK N O EC R c R09 M-86G (43B-C) EC R o R09 P-CCP #I 8445 EMER BORATE REV FLO CK 41C-C 2 C 2 CK N C EC R o RO1O V-3E5 (411B-B) EC R c RO10 V-18Q 8475 RECIP CH7G PP-3 DISCH4 CK 45D-B 2 C 2 CK N O EC R o ROI I P-PDP Tested Q (45B-C) EC R c ROI I V-25 9B26YL00.DOC 40MIS 36

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 21 OF52 CHEMICAL AND VOLUME CONTROL 'SYSTEM P& ID NO. 1020 08 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8478A CENT CHG PP-I DISCH CK 44D-C 2 C 4 CK N C CM CMP o/c V-181 (45B-B) 8478B CENT CHG PP-2 DISCH CK 44D-D 2 C 4 CK N C CM CMP 0/c V-181 (45B-A) 8479A CENT CHG PP-I RECIRC CK 44D-C 2 C 2 CK N C CM CMP o/c V-181 (44B-B) 8479B CENT CHG PP-2 RECIRC CK 44D-D 2 C 2 CK N C CM CMP o/c V-181 (45B-A) 8483 CHG FLO TO CL 3 BYPAS CK 42-B 2 C 314 CK N C EC R 0 R012 V-18D RV function (42-E) EC R C R012 V-18P 8487A BA TRANSFER PP-2 (PP-I) 52B-D 2 C 2 CK N 0 EC R 0 R013 P-BAT Tested Q DISCH CK (57B-B) EC R C R013 V-18R 8487B BA TRANSFER PP-I (PP-2) 52B-E 2 C 2 CK N 0 EC R 0 R013 P-BAT Tested Q DISCH CK (57B-A) EC R c RO13 V-18R RV-8116 PDP RV TO VCTI 44D-A 2 C 3/4x1 RV N C RT T 0 M-77 2720#

(44B-D)

RV-8117 LETDOWN RV TO PRT 44-C 2 C 2 RV N C RT T 0 M-77 600#

RV-8121 RCP SEAL WTR RETURN HDR RV 33B-A 2 C 2 RV N C RT T 0 M-77 150#

(37-E)

RV-8123 SEAL WTR HXI INLT RV TO VCT 43B-D NA C 2 RV N C RT T 0 M-77 150#

(41 B-D)

RV-8125 CHG PPS SUC HDR REL TO PZR 40D-B 2 C 3/4 RV N C RT T o M-77 220#

(431B-B) 9B26YL00.DOC 40MIS 37

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 22 OF 52 SAFETY INJECTION SYSTEM P& ID NO. 1020 09 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS S8161 FC-927 ISOL OC 42-E 2 A 3/4 GL M LC LT J c V-65 1B PASSIVE 8801A CHG INJ TO RCS 43-D 2 B 4 GA E C PI 2Y NA V-2J6 EF Q 10o V-3E9 8801B CHG INJ TO RCS 43-C 2 B 4 GA E C Pi 2Y NA V-2J6 EF Q 10o V-3E9 8802A SI PP-I DISCH ISOL OC 54-E 2 B 4 GA E LC PI 2Y NA V-2J6 EF CS 20o CS12 V-3LI 8802B Sl PP-2 DISCH ISOL OC 54-D 2 B 4 GA E LC PI 2Y NA V-2J6 EF CS 20o CS12 V-3LI 8803A CHG INJ TO RCS 45-C 2 B 4 GA E C Pi 2Y NA V-2C (45-B) EF Q 10o V-3Ell 8803B CHG INJ TO RCS 45-B 2 B 4 GA E C Pi 2Y NA V-2C EF Q 10o V-3EI I 8804A CHG PP SUCT FROM RHR 48-B 2 B 8 GA E C PI 2Y NA V-2V1 EF R 20o R014 V-3L16 8804B STPP SUCT FROM RHR 58-C 2 B 8 GA E C PI 2Y NA V-2VI EF R 200 R014 V-3L16 8805A RWST TO CHG PP SUCT 48-C 2 B *8 GA E C Pi 2Y NA V-2Z EF CS Ho CS13 V-3KI I 9B26YL00.DOC 40MIS 38

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 23 OF 52 SAFETY INJECTION SYSTEM P& ID NO. 1020 09 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8805B RWST TO CHARG PP SUCT 48-C 2 B 8 GA E C Pi 2Y NA V-2Z EF CS lo CS13 V-3KI I 8807A Si PP1 SUC TO CCP SUC XTIE 48-A 2 B 4 GA E C PI 2Y NA V-2H EF Q 20o V-3L3 8807B SI PPI SUC TO CCP SUC XTIE 48-A 2 B 4 GA E C PI 2Y NA V-2H EF Q 20o V-3L3 8808A ACCUM-I DISCH ISOL 31-D 2 B 10 GA E LO PI 2Y NA V-2PI EF CS 30o CS14 V-3L4 8808B ACCUM-2 DISCH ISOL 33-D 2 B 10 GA E LO PI 2Y NA V-2PI EF CS 30o CS14 V-3L4 8808C ACCUM-3 DISCH ISOL 35-D 2 B 10 GA E LO PI 2Y NA V-2PI EF CS 30o CS14 V-3L4 8808D ACCUM-4 DISCH ISOL 37-D 2 B 10 GA E LO PI 2Y NA V-2PI EF CS 30o CS14 V-3L4 8809A RHR TO CLD LEGS- 1&2 ISOL OC 54-C 2 B 8 GA E LO PI 2Y NA V-2J3 EF CS 20c CSI5 V-3L5 8809B RHR TO CLD LEGS-3&4 ISOL OC 54-B 2 B 8 GA E LO PI 2Y NA V-2J3 EF CS 20c CS15 V-3L5 8818A RHR TO COLD LEG-I CK 52-C I A,C 6 CK N C LT R* c V-5A2 *Per Tech Spec CM CMP o/c V-18B 8818B RHR TO COLD LEG-2 CK 52-B I A,C 6 CK N C LT R* c V-SA2 *Per Tech Spec CM CMP o/c V-18B 9B26YL00.DOC 40MIS 39

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 24 OF 52 SAFETY INJECTION SYSTEM P& ID NO. 1020 09 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8818C RHR TO COLD LEG-3 CK 51-B I A,C 6 CK N C LT R* C V-5A2 *Per Tech Spec CM CMP o/c V-18B 8818D RHRTO COLD LEG- CK 51-A 1 A,C 6 CK N C LT R* C V-5A2 *Per Tech Spec CM CMP o/c V-18B 8819A Si TO COLD LEG-I CK 52-C I A,C 2 CK N C LT R C V-SAI *Per Tech Spec EC R C RO15 V-5A1 EC R 0 R015 V-18D 8819B Si TO COLD LEG-2 CK 51-B I A,C 2 CK N C LT R* C V-5AI *Per Tech Spec EC R C R015 V-SAI EC R 0 R015 V-18D 8819C SI TO COLD LEG-3 CK 50-B I A,C 2 CK N C LT R* C V-SAI *Per Tech Spec EC R C R015 V-SAI EC R 0 ROI5 V-18D 8819D SI TO COLD LEG-4 CK 50-B I A,C 2 CK N C LT R* C V-SAI *Per Tech Spec EC R C R015 V-SAI EC R 0 R015 V-18D 8820 CHG INJ 2ND OFF CK 41-D I C 3 CK N C EC R C R016 V-SD EC R 0 R016 V-18D 8821A SI PP-I DISCH ISOL 55-E 2 B 4 GA E 0 PI 2Y NA V-2J6 EF Q 20c V-3L2A 8821B SI PP-2 DISCH ISOL 55-D 2 B 4 GA E 0 PI 2Y NA V-2J6 EF Q 20c V-3L2B 8835 SI COLD INJECT ISOL OC 54-C 2 B 4 GA E LO PI 2Y NA V-2J6 EF CS 20c CS16 V-3L6 9B26YL00.DOC 40MIS 40

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 25 OF 52 SAFETY INJECTION SYSTEM - --

P& ID NO. 1020 09 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8871 SI TEST LINE ISOL IC 38-C 2 A 3/4 GL A C PI 2Y NA V-201 LT J c V-651B EF Q lOc V-3S5 8875A SI ACCUM I NIT FILL & VENT 31-E 2 B I GL A C PI 2Y NA V-2P2 Passive 8875B SI ACCUM 2 NIT FILL & VENT 33-E 2 B I GL A C PI 2Y NA V-2P2 Passive 8875C SI ACCUM 3 NIT FILL & VENT 35-E 2 B I GL A C PI 2Y NA V-2P2 Passive 8875D SI ACCUM 4 NIT FILL & VENT 37-E 2 B I GL A C PI 2Y NA V-2P2 Passive 8876A SI ACCUM I DRAIN 30-D 2 B I GL A C PI 2Y NA V-2P2 Passive 8876B SI ACCUM 2 DRAIN 32-D 2 B I GL A C PI 2Y NA V-2P2 Passive 8876C SI ACCUM 3 DRAIN 34-D 2 B I GL A C PI 2Y NA V-2P2 Passive 8876D SI ACCUM 4 DRAIN 37-D 2 B I GL A C PI 2Y NA V-2P2 Passive 8880 N2 SUP TO ACCUM ISOL OC 39-E 2 A I GL A 0 PI 2Y NA V-2J7 LT J c V-651A Tested R EF Q 10c V-3S5 8883 SI PP-I TO TST LINE ISO OC 54-E 2 A 3/4 GL A C PI 2Y NA V-2J7 LT J c V-651B EF Q loc V-3S5 8900A CHG INJ LOOP-I CK 40-E I C 1.5 CK N C EC R o R016 V-18D EC R c R016 V-5D 8900B CHG INJ LOOP-2 CK 40-B I C 1.5 CK N C EC R o R016 V-18D EC R c R016 V-SD 8900C CHG INJ LOOP-3 CK 40-C I C 1.5 CK N C EC R o R016 V-18D EC R c R016 V-SD 8900D CHG INJ LOOP-4 CK 40-D I C 1.5 CK N C EC R o R016 V-18D EC R c R016 V-5D 9B26YL00.DOC 40MIS 41

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 26 OF 52 SAFETY INJECTION SYSTEM P& ID NO. 1020 09 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8905A SI TO HOT LEG-I CK 52-E I A,C 2 CK N C EC R 0 RO15 V-18D EC R c RO1S V-SC LT R* c V-SC *Per Tech Spec 8905B SI TO HOT LEG-2 CK 52-E I A,C 2 CK N C EC R 0 RO1S V-18D EC R C RO15 V-SC LT R* C V-5C *Per Tech Spec 8905C SI TO HOT LEG-3 CK 51-D I A,C 2 CK N C EC R 0 ROIS V-18D EC R c RO15 V-5C LT R* C V-SC *Per Tech Spec 8905D SI TO HOT LEG-4 CK 51-D I A,C 2 CK N C EC R 0 RO15 V-18D EC R C RO15 V-5C LT R* C V-SC *Per Tech Spec 8916 N2 SUP TO ACCUM CK IC 38-E 2 A,C I CK N C LT J c V-651A Tested R EC R c R03 V-651A EC R 0 R03 #1 8919A SI PP-I TO RWST CK 57-E 2 C 3/4 CK N C EC R 0 R017 P-SIP Tested Q EC R c RO17 V-24 8919B SI PP-2 TO RWST CK 57-D 2 C 3/4 CK N C EC R 0 R017 P-SIP Tested Q EC R c R017 V-24 8922A SI PP-I DISCH CK 56-E 2 C 4 CK N C EC R 0 R018 V-18D EC R c R018 P-SIP Tested Q 8922B SI PP-2 DISCH CK 56-D 2 C 4 CK N C EC R 0 R018 V-18D EC R c R018 P-SIP Tested Q 8923A SI PP-I SUCT 58-E 2 B 6 GA E 0 PI 2Y NA V-2H EF Q 30c V-3L1tOA 8923B SI PP-2 SUCT 58-D 2 B 6 GA E 0 PI 2Y NA V-2H EF Q 30c V-3L1 OB 8924 RWST TO CHG PP CK 48-C 2 C 8 CK N C EC R 0 R019 V-18D EC R c R019 M-86G 9B26YL00.DOC 40MIS 42

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 27 OF 52 SAFETY INJECTION SYSTEM P& ID NO. 1020 09 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8948A LOOP-1 COLD INJ CK 30-C I A,C 10 CK N C LT R* C V-5A2 *Per Tech Spec CM CMP o/c V-18A 8948B LOOP-2 COLD INJ CK 30-B I A,C 10 CK N C LT R* C V-5A2 *Per Tech Spec CM CMP o/c V-18A 8948C LOOP-3 COLD INJ CK 30-B I A,C 10 CK N C LT R* C V-5A2 *Per Tech Spec CM CMP o/c V-18A 8948D LOOP-4 COLD INJ CK 30-A I A,C 10 CK N C LT R* C V-5A2 *Per Tech Spec CM CMP o/c V-18A 8949A SI TO HOT LEG-I CK 50-E I A,C 6 CK N C EC R 0 R020 V-18D EC R C R020 V-SC LT R* C V-5C *Per Tech Spec 8949B Sl TO HOT LEG-2 CK 50-E I A,C 6 CK N C EC R 0 R020 V-18D EC R C R020 V-5C LT R* C V-5C *Per Tech Spec 8949C SI TO HOT LEG-3 CK 50-D I A,C 6 CK N C EC R 0 R020 V-18D EC R C R020 V-5C LT R* C V-SC *Per Tech Spec 8949D SI TO HOT LEG-4 CK 50-D I A,C 6 CK N C EC R 0 R020 V-18D EC R C R020 V-SC LT R* C V-SC *Per Tech Spec 8956A ACCUM-1 DISCH CK 31-C I A,C 10 CK N C LT R* C V-5AI *Per Tech Spec CM CMP 0/c V-18A 8956B ACCUM-2 DISCH CK 31-B I A,C 10 CK N C LT R* C V-SAI *Per Tech Spec CM CMP o/c V-18A 8956C ACCUM-3 DISCH CK 31-B I A,C 10 CK N C LT R* C V-SAI *Per Tech Spec CM CMP o/c V-18A 8956D ACCUM-4 DISCH CK 31-A I A,C 10 CK N C LT R* C V-SAI *Per Tech Spec CM CMP o/c V-18A 9B26YL00.DOC 40MIS 43

PAtCIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 28 OF 52 SAFETY INJECTION SYSTEM P& ID NO. 1020 09 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8961 SI TEST LINE ISOL OC 39-C 2 A 3/4 GL A C PI 2Y NA V-2J7 LT J c V-651B EF Q 10c V-3S5 8974A SI RECIRC TO RWST 58-D ISTC. B 2 GL E LO PI 2Y NA V-2V2 EF CS l0c CS17 V-3L15 8974B SI RECIRC TO RWST 57-D 2 B 2 GL E LO PI 2Y NA V-2V2 EF CS loc CS17 V-3L15 8976 RWST TO S1 PP ISOL 59-D 2 B 8 GA E LO PI 2Y NA V-2J6 EF CS 20c CS18 V-3L13 8977 .RWST TO SI PP CK 59-D 2 C 8 CK N C EC R o R021 V-15 EC R c R021 M-86AI 8980 RWST TO RHR PPS ISOL OC 59-B 2 B 12 GA E LO PI 2Y NA V-2J3 EF CS 25c CS19 V-3L14 8981 RWST TO RHR PP CK 59-B 2 C 12 CK N C EC R o R022 V-4C EC R c R022 V-4D 8982A CONT RCRC SMP TO RHRPI ISO 52-A 2 B 14 GA E LC PI 2Y NA V-206 EF R 25o R023 V-3L17 8982B CONT RCRC SMP TO RHRP2 ISO 53-A 2 B 14 GA E LC PI 2Y NA V-206 EF R 25o R023 V-3L17 RV-8851 SI TO CL RELIEF TO PRT 55-D 2 C 3/4 RV N C RT T o M-77 1750#

RV-8853A SI PPI DISCH TO PRT RV 55-E 2 C 3/4xl RV N C RT T o M-77 1750#

RV-8853B SI PP2 DISCH TO PRT RV 54-D 2 C 3/4xl RV N C RT T o M-77 1750#

RV-8855A ACCUM I PRES RV 31-E 2 C I RV N C RT T o M-77 700#

RV-8855B ACCUM 2 PRES RV 33-E 2 C I RV N C RT T o M-77 700#

RV-8855C ACCUM 3 PRES RV 36-E 2 C I RV N C RT T o M-77 700#

9B26YL00.DOC 40MIS 44

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 29 OF 52 SAFETY INJECTION SYSTEM P& ID NO. 1020 09 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS RV-8855D ACCUM 4 PRES RV 38-E 2 C 1 RV N C RT T o M-77 700#

RV-8856A RHR PP1 DISCH TO PRT RV 54-B 2 C 2X3 RV N C RT T o M-77 606#

RV-8856B RHR PP2 DISCH TO PRT RV 54-B 2 C 2X3 RV N C RT T o M-77 606#

RV-8858 RWST TO ST PP SUCT RV 58-D 2 C 3/4 RV N C RT T o M-77 2201 9B26YL00.DOC 40MIS 45

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 30 OF 52 RESIDUAL HEAT REMOVAL SYSTEM P& ID NO. 1020 10 VALVE VALVE P &ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FCV-64 IA RHR PP-I RECIRC 34-E 2 B 2 GL E C PI 2Y NA V-2D EF Q IOo/c V-3MIA FCV-641B RHR PP-2 RECIRC 34-B 2 B 2 GL E C PI 2Y NA V-2D EF Q IOo/c V-3MIB HCV-637 RHR HX-2 OUTLET 31-B 2 B 8 BA A 0 EF Q 30O V-3M2B (31-C) PI 2Y NA V-2J3 HCV-638 RHR HX-I OUTLET 31-D 2 B 8 BA A 0 EF Q 30o V-3M2A Pl 2Y NA V-2J3 8700A RHR PP- I SUCT OC 37-D 2 B 14 GA E 0 PI 2Y NA V-2D2 (36-D) EF Q 120c V-3M4A 8700B RHR PP-2 SUCT OC 37-B 2 B 14 GA E 0 PI 2Y NA V-2D2 (36-B) EF Q 120c V-3M4B 8701 RCS LOOP-4 TO RHR IC 38-D I A 14 GA E LC PI 2Y NA V-2D3 LT R* C V-7C *Per Tech Spec EF CS 160o/c CS20 V-3M5 8702 RCS LOOP-4 TO RHR 39-D I A 14 GA E LC P1 2Y NA V-2D3 (38-D) LT R* C V-7C *Per Tech Spec EF CS 160o/c CS20 V-3M5 8703 RHR TO HOT LEGS-I, 2 IC 38-A 2 A 12 GA E LC PI 2Y NA V-2M3 EF CS 85o CS21 V-3M6 LT R* C V-5C *Per Tech Spec 9B26YL00.DOC 40MIS 46

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 31 OF 52

. RESIDUAL HEAT REMOVAL SYSTEM P& ID NO. 1020 10 VALVE VALVE P&ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8716A RHRTRAINXTIEOC 30-D 2 B 8 GA E 0 PI 2Y NA V-2J3 EF CS 20o/c CS22 V-3M7 8716B RHR TRAIN XTIE OC 30-C 2 B 8 GA E 0 Pl 2Y NA V-2J3 EF CS 20o/c CS22 V-3M7 8730A RHR PP-I DISCH CK 35-D 2 C 8 CK N C CM CMP o/c P-RHR-A 8730B RHR PP-2 DISCH CK 35-B 2 C 8 CK N C CM CMP o/c P-RHR-A (35-C) 8740A RHR TO HOT LEG-I CK 39-B I A/C 8 CK N C CM CMP o/c V-18C LT R* C V-SC *Per Tech Spec 8740B RHR TO HOT LEG-2 CK 39-A 1 A/C 8 CK N C CM CMP o/c V-18C LT R* C V-5C *Per Tech Spec 8742A RH-R HT EX-l DISCH CK 32-D 2 C 8 CK N C EC CS a CS23 V-4B EC CS C CS23 P-RHR Tested Q 8742B RHR HT EX-2 DISCH CK 32-B 2 C 8 CK N C EC CS 0 CS23 V-4B (32-C) EC CS c CS23 P-RHR Tested Q RV-8707 RHR PPS SUCT FROM HL4 RV 38-D 2 C 3x4 RV N C RT T 0 M-77 455#

(37-D)

RV-8708 RHR TO HLI&2 TO PRT RV 38-B 2 C 3/4xl RV N C RT T o M-77 606#

(37-B) 9B26YL00.DOC 40MIS 47

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 32 OF 52 NUCLEAR STEAM SUPPLY SAMPLING SYSTEM P& IDNO. 1020 11 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM T!ST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 9354A PZR STM SAMPLE ISOL IC 21-A 2 A 3/8 GL A 0 PI 2Y NA V-203 L'r J c V-676A ElF Q lOc V-3SI 9354B PZR STM SAMPLE ISOL OC 22-A 2 A 3/8 GL A 0 P1 2Y NA V-2JI I

L' J c V-676A E] Q 1Oc V-3SI 9355A PZR LIQUID SAMPLE ISOL IC 21-B 2 A 3/8 GL A 0 PI.F 2Y NA V-203 LT J c V-659A E]F Q lOc V-3SI 9355B PZR LIQUID SAMPLE ISOL OC T 22-B 2 A 3/8 GL A 0 PF 2Y NA V-2JI L i c V-659A E Q lOc V-3SI 9356A T HOT LEG SAMPLE ISOL IC 21-B 2 A 3/8 GL A O P1. 2Y NA V-203 F

L' J c V-659B E] Q lOc V-3SI 9B26YLOO.DOC 4OMIS 48

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 33 OF 52 NUCLEAR STEAM SUPPLY SAMPLING SYSTEM P& ID NO. 1020 11 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 9356B HOT LEG SAMPLE ISOL OC 22-B 2 A 3/8 GL A 0 Pi 2Y NA V-2JI LT J c V-659B EF Q 1Oc V-3SI 9357A ACCUM SAMPLE ISOL IC 21-C 2 A 3/8 GL A 0 Pi 2Y NA V-203 LT J c V-659C EF Q lOc V-3SI 9357B ACCUM SAMPLE ISOL OC C 2 A 3/8 GL A 0 Pi 2Y NA V-2JI LT J c V-659C EF Q lOc V-3SI 9B26YL00.DOC 40MIS 49

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 34 OF 52 CONTAINMENT SPRAY SYSTEM P& ID NO. 1020 12 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS CS-31 CS PP-I TO MEDT ISOL OC 33-D 2 A .75 GL M LC LT J c V-631 PASSIVE Tested R CS-32 CS PP-2 TO MEDT ISOL OC 33-B 2 A .75 GL M LC LT J c V-630 PASSIVE Tested R 8992 CS ADD TK STOP 37-B 2 B 3 GA E LO PI 2Y NA V-2G PASSIVE 8994A NaOH CS EDUCTOR ISOL 36-B 2 B 3 GA E C PI 2Y NA V-2G EF CS oo CS24 V-312 8994B NaOH CS EDUCTOR ISOL 37-B 2 B 3 GA E C PI 2Y NA V-2G EF CS I oo CS24 V-312 8998A CS ADD TK OUT CK 35-C 2 A,C 3 CK N C EC R 0 R024 V-3II LT 2Y V-21

,c EC R R024 V-21 8998B CS ADD TK OUT CK 35-B 2 A,C 3 CK N C EC R 0 R024 V-311 LT 2Y c V-21 EC R c R024 V-21 9001A CS PP-I ISOL 34-D 2 A 8 GA E C PI 2Y NA V-2B LT J c V-631 Tested R EF Q oo V-313A 9001B CS PP-2 ISOL 34-A 2 A 8 GA E C PI 2Y NA V-2B LT J c V-630 Tested R EF Q Io V-313B 9B26YL00.DOC 40MIS 50

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 35 OF 52 CONTAINMENT SPRAY SYSTEM P& ID NO. 1020 12 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 9002A CS PP-I DISCH CK 33-D 2 C 8 CK N C CM CMP o/c CSP-A 9002B CS PP-2 DISCH CK 33-A 2 C 8 CK. N C CM CMP o/c CSP-A 9003A RHR HX-I TO CS-A HDR 33-D 2 B 8 GA E C Pi 2Y NA V-2B2 EF R 1So R014 V-3I4 9003B RHR HX-2 TO CS-B HDR 33-B 2 B 8 GA E C PI 2Y NA V-2B2 EF R 150 R014 V-3I4 901 IA CS HDR-A ISOL CK IC 32-D 2 A,C 8 CK N C LT J c V-631 Tested R CM CMP o/c M-86H 901 1B CS HDR-B ISOL CK IC 32-A 2 A,C 8 CK N C LT J c V-630 Tested R CM CMP o/c M-86H RV-930 CS ADD TKI VAC BREAK 37-D 2 C 1.5 RV N C RT T 0 M-77 -l.Sf vac RV-931 CS ADD TK2 VAC BREAK 37-C 2 C 1.5 RV N C RT T 0 M-77 1,5# vac RV-8987 CS ADD TKI TO AUX BLDG SMP 38-C 2 C 3/4xl RV N C RT T 0 M-77 10#

RV-9007A CS HDR A OC RV 32-D 2 C 3/4 RV N C RT T 0 M-77 260#

RV-9007B CS HDR B OC RV 32-B 2 C 3/4 RV N C RT T 0 M-77 260#

9B26YL00.DOC 40MIS 51

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 36 OF 52 COMPONENT COOLING WATER SYSTEM P& ID NO. 1020 14 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS CCW-4 SUCT X-TIE VLV 50-C 3 B 20 BV M LO EF 2Y NA V-3H15 BETWEEN HDRS B&C CCW-5 SUCT X-TIE VLV 52-C 3 B 20 BV M LO EF 2Y NA V-3H15 BETWEEN HDRS A&C CCW-16 CCW PP 2 DISCH 53-D 3 B 20 BV M LO EF 2Y NA P-CCW Tested Q TO HEADER B CCW-17 CCW PP 3 DISCH 54-D 3 B 20 BV M LO EF 2Y NA P-CCW Tested Q TO HEADER B (55-D)

CCW-18 CCW PP 1 DISCH 51-E 3 B 20 BV M LO EF 2Y NA P-CCW Tested Q TO HEADER A CCW-19 CCW PP 2 DISCH 53-E 3 B 20 BV M LO EF 2Y NA P-CCW Tested Q TO HEADER A CCW-23 CCW HEADER A TO C 58-E 3 B 24 BV M LO EF 2Y NA P-CCW Tested Q ISOLATION VALVE CCW-24 CCW HEADER B TO C 58-D 3 B 24 BV M LO EF 2Y NA P-CCW Tested Q ISOLATION VALVE I

9B26YL00.DOC 40MIS 52

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 37 OF 52 COMPONENT COOLING WATER SYSTEM P& ID NO. 1020 14 VALVE VALVE P&ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COOR CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS D

CCW-581 CCW FCV-749 BYPASS CK IC 71-B 2 A,C 3/4 CK N C LT R C V-620 Tested R EC R 0 ROS V-620 RV function EC R C RO5 V-620 CCW-585 CCW TO RCP & RX VSL 72-E 2 A,C 10 CK N 0 LT J C V-619 Tested R SUPPORT CK IC EC R C R03 V-619 EC R 0 R03 #l CCW-601 CCW PP-I 1HDR-A CK 51-E 3 C 20 CK N 0 CM CMP 0/c V-CCW-CK PEP CCW-602 CCW PP-2 HDR-A CK 53-E 3 C 20 CK N 0 CM CMP 0/c V-CCW-CK PEP CCW-603 CCW PP-3 HDR-A CK - 54-E 3 C 20 CK N 0 CM CMP o/c V-CCW-CK PEP (55-E)

CCW-607 CCW PP-I HDR-B CK 51-D 3 C 20 CK N 0 CM CMP o/c V-CCW-CK PEP CCWV-608 CCW PP-2 HDR-B CK 53-D 3 C 20 CK N 0 CM CMP o/c V-CCW-CK PEP CCW-609 CCW PP-3 HDR-B CK 54-D 3 C 20 CK N 0 CM CMP o/c V-CCW-CK PEP (55-D)

CCW-670 CCW FCV-750 BYPASS CK IC 73-B 2 A,C 3/4 CK N C LT J C V-621 Tested R EC R 0 ROS V-621 RV function EC R C RO5 V-621 c

CCW-695 CCW TO EXCS LTDN HX CK OC 98-D 2 A,C 4 CK N 0 LT J V-623 Tested R c

EC R R03 V-623 EC R 0 R03 #1 FCV-355 CCW HDR-C ISOL 58-D 3 B 20 BV E 0 PI 2Y NA V-2F (59-D) EF CS 20c CS25 V-3H3 RRI FCV-356 CCW TO RCP & RX VSL 72-E - 2 A 10 BV E 0 PI 2Y NA V-2J2 SUPPORT ISOL OC LT J c V-619 Tested R EF CS 25c CS25 V-31-14 RRI FCV-357 RCP THM BAR CCW RTN ISO OC 73-B 2 A 6 GL E 0 Pi 2Y NA V-2J2 LT J C V-621 Tested R EF CS 30c CS25 V-3H5 RRI 9B26YL00.DOC 40MIS 53

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 38 OF 52 COMPONENT COOLING WATER SYSTEM P& ID NO. 1020 14 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FCV-361 CCW FRM XCS LTDN HX ISO OC 98-B -2 A 4 BV A C Pi 2Y NA V-2J2 LT J c V-623 Tested R EF Q lOc V-3S6 FCV-363 RCP'S CLR CCW RTN ISOL OC 72-B 2 A 6 BV E 0 PI 2Y NA V-2J2 LT J c V-620 Tested R EF CS 25c CS25 V-3H6 RRI FCV-364 RHR HX-2 CCW RETURN 60-C 3 B 12 BV A C Pi 2Y NA V-2H EF Q 10o V-3H7 FCV-365 RHR HX-1 CCW RETURN 104-C 3 B 12 BV A C Pi 2Y NA V-2H EF Q 10o V-3H7 FCV-430 CCW HX-1 OUT ISOL 57-E 3 B 30 BV E 0 PI 2Y NA V-2F (58-E) EF Q 30O V-3H8 FCV-431 CCW HX-2 OUT ISOL 57-D 3 B 30 BV E 0 PI 2Y NA V-2F (58-D) EF Q 30O V-3H8 FCV-749 RCP'S CLR CCW RTN ISOL IC 72-B 2 A 6 BV E 0 PI 2Y NA V-202 LT J c V-620 Tested R EF CS 20c CS25 V-3H10 RRI FCV-750 RCP THM BAR CCW RTN ISO IC 73-B 2 A 6 GL E 0 PI 2Y NA V-202 LT J c V-621 Tested R EF CS 30c CS25 V-3H9 RRI LCV-69 MU WTR TO CCW HDR-A 55-B 3 B 3 GL A C EF Q 20o V-3111 I LCV-70 MU WTR TO CCW HDR-B 55-B 3 B 3 GL A C EF Q 20o V-3H11 RCV-16 CCW SURGE TK VENT 56-C 3 B 3 BA A 0 PI 2Y NA V-2F EF Q 1Oc V-3H12 9B26YL00.DOC 40MIS 54

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 39 OF 52 COMPONENT COOLING WATER SYSTEM P& ID NO. 1020 14 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS RV-41 RCP3 THRML BARRIER CCW RTN 72-C 3 C 3/4xl RV N C RT T 0 M-77 2485#

RV-42 RCP4 THRML BARRIER CCW RTN 73-C 3 C 3/4xl RV N C RT T 0 M-77 2485#

RV-43 RCP2 THRML BARRIER CCW RTN 70-C 3 C 3/4xl RV N C RT T 0 M-77 2485#

RV-44 RCP1 THRML BARRIER CCW RTN 74-C 3 C 3/4xl RV N C RT .T 0 M-77 2485#

RV-45 CCW SURGE TANK RV 57-C 3 C 3x4 RV N C RT T 0 M-77 30#

RV-46 FCV-365 BYPASS RV 103-C 3 C 3/4xl RV N C RT T 0 M-77 70#

RV-47 CCW RTN FROM RHR HX2 RV 61-C 3 C 3/4xl RV N C RT T 0 M-77 70#

RV-51 RCP'S LO CLG RTN TO CCW RV 72-C 3 C 3 RV N C RT T 0 M-77 150#

RV-52 CCW RTN XCES LTDN HX RV 98-C 2 C 3 RV N C RT T 0 M-77 150#

9B26YL00.DOC 40MIS 55

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 40 OF 52 MAKEUP WATER SYSTEM P& ID NO. 1020 16 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS MU-963 AFW PP RECIRC TO CST CK 71-C 3 C 2 CK N C CM CMP 0/c V-18 (78-C)

MU-965 CST TO MU H20 XFR PPS CK 70-D 3 C 4 CK N C CM CMP o/c V-18 (78-D)

MU-966 MU WATER PP RECIRC CK 73-D 3 C 4 CK N 0 CM CMP o/c V-18 MU-968 MU H20 XFR PP-01 DISCH CK 74-D 3 C 4 CK N C CM CMP o/c P-MUW-A1 MU-969 MU WATER PP RECIRC CK 76-D 3 C 4 CK N 0 CM CMP o/c V-18 MU-970 MU H20 XFR PP-02 DISCH CK 75-D 3 C 4 CK N C CM CMP o/c P-MUW-A2 MU-971 MU H20 TO MISC SOURCES CK 72-E 3 C 4 CK N C EC R o R025 V-3U2 (78-E) EC R c R025 V-3U3 MU-1555 CST H20 MIXING PP DISCH CK 71-C 3 C 3 CK N 0 EC Q c V-3UI (78-D) EC Q 0 V-3UI MU-1557 RAW WATER SUPPLY 57A-D 3 B 8 BV M LC EF 2Y NA P-MUW-A HDR ISOL 9B26YL00.DOC 40MIS 56

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 41 OF 52 SALTWATER SYSTEM P& ID NO. 1020 17 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS SW-34 ASW PP-I DISCH VAC RELIEF 32B-D 3 C 3 CK N C EC 2Y o/c V-18M VAC Breaker SW-170 ASW PP-I DISCH VAC RELIEF 32B-D 3 C 3 CK N C EC 2Y o/c V-18M VAC Breaker SW-200 ASW PP-I DISCH CK 32B-A 3 C 24 CK N 0 EC Q o/c P-ASW SW-201 ASW PP-2 DISCH CK 32B-C 3 C 24 CK N 0 EC Q o/c P-ASW SW-301 ASW PP-2 DISCH VAC RELIEF 31B-D 3 C 3 CK N C EC 2Y o/c V-18M VAC Breaker SW-303 ASW PP-2 DISCH VAC RELIEF 31B-D 3 C 3 CK N C EC 2Y o/c V-18M VAC Breaker FCV-495 ASW PP-2 CROSS TIE 33B-B 3 B 24 BV E,M 0 PI 2Y NA V-2AI EF Q 30 o/c V-3F1 EF 2Y NA V-2AI Manual Stroke FCV-496 ASW PP-I CROSS TIE 33B-B 3 B 24 BV E,M 0 PI 2Y NA V-2AI EF Q 30 o/c V-3F2 EF 2Y NA V-2AI Manual Stroke FCV-601 ASW UNIT CROSS TIE 33B-B 3 B 24 BV E C PI 2Y NA V-2A2 EF Q 30o V-3F3 EF 2Y NA V-2A2 Manual Stroke FCV-602 CCW HX-I SW INLET 35B-A 3 B 24 BV A 0 PI 2Y NA V-2F EF Q 60o V-3F4 UNIT I (EF Q 120o V-3F4 UNIT 2)

FCV-603 CCW HX-2 SW INLET 35B-C 3 B 24 BV A 0 PI 2Y NA V-2F EF Q 60o V-3F5 UNIT I (EF Q 900 V-3F5 UNIT 2) 9B26YL00.DOC 40MIS 57

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 42 OF 52 FIRE PROTECTION SYSTEM P& ID NO. 1020 18 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FP-180 CONT FIREWATER ISOL IC 73-B 2 A,C 4 CK N C LT J c V-679 (FP-867) (73-D) EC R c R026 V-679 EC R o R026 M-63H FCV-633 CONT FIREWATER ISOL OC 72-B 2 A 3 GL A 0 PI 2Y NA V-2J7 I(72-E) LT i NA V-679 EF Q lOc V-3S4 FP-306 FIREWATER SUPPLY TO 37-C 3 B 8 BV M C EF Q* NA V-3P4 *Per Tech Specs AUX FEED PPS FP-307 FIREWATER SUPPLY TO 37-C 3 B 8 BV M C EF Q* NA V-3P4 *Per Tech Specs AUX FEED PPS 9B26YL00.DOC 40MIS 58

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 43 OF 52 LIQUID RADWASTE SYSTEM P& ID NO. 1020 19 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS LWS-60 N2 TO RCDT ISOL TC 38-C 2 A,C 3/4 CK N C LT J c V-652D Tested R EC R R03 V-652D EC R 0 R03 FCV-253 RCDT PP DISCH ISOL IC 38-A 2 A 2.5 BA A 0 PI 2Y NA V-205 LT i c V-650 EF Q lOc V-3S3 FCV-254 RCDT PP DISCH ISOL OC 39-A 2 A 2.5 BA A 0 PI 2Y NA V-2J5 LT J c V-650 EF Q lOc V-3S3 FCV-255 RCDT VENT ISOL IC 38-B 2 A 3/4 BA A 0 PI 2Y NA V-205 LT J c V-651C EF Q lOc V-3S3 FCV-256 RCDT VENT ISOL OC 39-B 2 A 3/4 BA A 0 PI 2Y NA V-2J5 LT i c V-651C EF Q 1Oc V-3S3 FCV-257 RCDT GAS ANAL ISOL OC 39-B 2 A 1/2 BA A C Pi 2Y NA V-2J5 LT i c V-651D EF Q lOc V-3S3 9B26YL00.DOC 40MIS 59

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 44 OF 52 LIQUID RADWASTE SYSTEM P& ID NO. 1020 19 VALVE VALVE P & ID VLV VLV V'LV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT S;IZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FCV-258 RCDT GAS ANAL ISOL IC 38-B 2 A I1/2 BA A 0 PI 2Y NA V-205 LT J c V-651 D EF Q lOc V-3S3 FCV-260 N2 TO RCDT ISOL OC 38-C 2 A 2/4 BA A 0 PI 2Y NA V-2J5 LT i c V-652D Tested R EF Q lOc V-3S3 FCV-500 CONT SUMP DISCH ISOL IC 38-D 2 A 2 BA A 0 PI 2Y NA V-205 LT i c V-649 EF Q 1Oc V-3S3 FCV-501 CONT SUMP DISCH ISOL OC 39-D 2 A 2 BA A 0 PI 2Y NA V-2J5 LT i c V-649 EF Q lOc V-3S3 FCV-696 RX CAV SUMP SMPL SUP ISO IC 38-B 2 A 3/8 GL S C PI 2Y NA V-682A LT i c V-682A Tested R EF CS 10o CS26 V-3T5 FCV-697 RX CAV SUMP SMPL SUP ISO OC 39-B 2 A 3/8 GL S C PI 2Y NA V-682A LT J c V-682A Tested R EF CS 1Oo CS26 V-3T5 9B26YL00.DOC 40MIS 60

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 45 OF 52 LIQUID RADWASTE SYSTEM P& ID NO. 1020 19 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS 8767 REFUEL WTR PURIF ISOL OC 39-C 2 A 4 DI M LC LT J C V-646 PASSIVE 8787 REFUEL WTR PURIF ISOL OC 39-D 2 A 4 DI M LC LT J c V-646 PASSIVE 8795 REFUEL WTR PURIF ISOL IC 38-C 2 A 4 DI M LC LT J c V-646 PASSIVE 8796 REFUEL WTR PURIF ISOL IC 38-D 2 A 4 DI M LC LT J C V-646 PASSIVE 9B26YL00.DOC 40MIS 61

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 46 OF 52 VENTILATION AND AIR CONDITIONING SYSTEM P& ID NO. 1020 23 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS VAC-1 CHP SUP FAN-I ISOL OC 34-A 2 A 4 GA M LC LT J c V-683 PASSIVE Tested R VAC-2 CHP SUP FAN-2 ISOL OC 34-A 2 A 4 GA M LC LT J c V-683 PASSIVE Tested R VAC-21 CONT AIR SMPL RTN ISOL IC 44-B 2 A,C 2 CK N 0 LT J c V-668 CM CMP o/c V-18 VAC-116 CONT AIR SMPL POST LOCA. 44-C 2 A,C 3/8 CK N C LT R c V-682B Tested R RTN ISOL IC EC R C R03 V-682B EC R 0 R03 #1 VAC-200 CHP SUP ISOL IC CK 35-A 2 A,C 4 CK N C LT J C V-683 Tested R CM CMP o/c V-18 VAC-201 CHP SUP ISOL IC CK 35-A 2 A,C 4 CK N C LT J c V-683 Tested R CM CMP 0o/C V-18 VAC-252 CONT H2 SAMPLE RTN CK IC 44-D 2 A,C 3/8 CK N C LT J C V-678 Tested R EC R 0/C R027 V-678 VAC-253 CONT H2 SAMPLE RTN CK IC 44-E 2 A,C 3/8 CK N C LT J C V-678 Tested R (44-D) EC R o/C R027 V-678 FCV-235 CONT H2 SAMPLE SUP ISOL IC 44-C 2 A 3/8 GL S LC PI 2Y NA V-678 LT J C V-678 Tested R EF CS I oo CS26 V-3T3 9B26YL00.DOC 40MIS 62

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 47 OF 52 VENTILATION AND AIR CONDITIONING SYSTEM P& ID NO. 1020 23 VALVE VALVE P & ID VLV VLV VIIV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SI,Z TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FCV-236 CONT H2 SAMPLE SUP ISOL OC 46-C 2 A 3/'8 GL S LC PI 2Y NA V-678 LT J c V-678 Tested R EF CS 10o CS26 V-3T3 FCV-237 CONT H2 SAMPLE RTN ISOL OC 46-D 2 A 3/'8 GL S LC Pl 2Y NA V-678 LT J c V-678 Tested R EF CS 10o CS26 V-3T3 FCV-238 CONT H2 SAMPLE SUP ISOL IC 44-D 2 A 3//8 GL S LC PI 2Y NA V-678 LT J c V-678 Tested R EF CS 10o CS26 V-3T3 FCV-239 CONT H2 SAMPLE SUP ISOL OC 46-D 2 A 3/'8 GL S LC Pl 2Y NA V-678 LT J c V-678 Tested R EF CS 10o CS26 V-3T3 FCV-240 CONT H2 SAMPLE RTN ISOL OC 46-E 2 A 3/'8 GL S LC Pl 2Y NA V-678 (46-D) LT i c V-678 Tested R EF CS 10o CS26 V-3T3 9B26YL00.DOC 40MIS 63

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 48 OF 52 VENTILATION AND AIR CONDITIONING SYSTEM P& ID NO. 1020 23 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FCV-658 CHP EXH SYS #2 DISCH ISO IC 35-B 2 A 4 GA E LC PI 2Y NA V-2X LT J C V-681 Tested R EF CS 150 CS26 V-3T3 FCV-659 CHP EXH SYS #I DISCH ISO IC 35-B 2 A 4 GA E LC PI 2Y NA V-2X LT J c V-657 Tested R EF CS 150 CS26 V-3T3 FCV-660 CONT PURGE SUP ISOL IC 35-C 2 A 48 BV A C PI 2Y NA V-2Q LT 2Y* c V-661 *Per Tech Spec EF CS 2c CS27 V-3T7 FCV-661 CONT PURGE SUP ISOL OC 34-C 2 A 48 BV A C PI 2Y NA V-2EI LT 2Y* C V-661 *Per Tech Spec EF CS 2c CS27 V-3T7 FCV-662 CONT EXCESS PRESNVAC RLF 35-B 2 A 12 BV A C PI 2Y NA V-2Q ISOL IC LT 2Y* C V-663 *Per Tech Spec EF Q Sc V-3T6 9B26YL00.DOC 40MIS 64

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 49 OF 52 VENTILATION AND AIR CONDITIONING SYSTEM P& ID NO. 1020 23 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FCV-663 CONT XCESS PRES RLF ISO OC 31-B 2 A 12 BV A C PI 2Y NA V-2E3 LT 2Y* C V-663 *Per Tech Spec EF Q Sc V-3T6 FCV-664 CONT VAC RLF OC 32-C 2 A 12 BV A C PI 2Y NA V-2E3 LT 2Y* C V-663 *Per Tech Spec EF Q Sc V-3T6 FCV-668 CHP EXH SYS #2 DISCH ISO OC 34-B 2 A 4 GA E LC PI 2Y NA V-2X LT J C V-681 Tested R EF CS 15o CS26 V-3T3 FCV-669 CHP EXH SYS # IDISCH ISO OC 34-B 2 A 4 GA E LC PI 2Y NA V-2X LT J C V-657 Tested R EF CS 150 CS26 V-3T3 FCV-678 CONT AIR SAMPLE SUP ISOL IC 44-A 2 A I BA A 0 PI 2Y NA V-203 LT J C V-668 Tested R EF Q lOc V-3TI 9B26YL00.DOC 40MIS 65

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 50 OF 52 VENTILATION AND AIR CONDITIONING SYSTEM P& ID NO. 1020 23 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS FCV-679 AIR SAMPLE SUP ISOL OC 46-A 2 A I BA A 0 PI 2Y NA V-2JI LT J C V-668 Tested R EF Q lOc V-3TI FCV-681 AIR SAMPLE RETURN ISOL OC 46-B 2 A I BA A 0 PI 2Y NA V-2JI LT i C V-668 Tested R EF Q 1Oc V-3TI FCV-698 AIR SAMPLE POST LOCA SUP 44-B 2 A 3/8 GL S C PI 2Y NA V-682B Tested R ISOL OC LT R C V-682B Tested R EF Q 10Oo/c V-3T4 FCV-699 AIR SAMPLE POST LOCA SUP 46-B 2 A 3/8 GL S C PI 2Y NA V-682B Tested R ISOL OC LT i C V-682B Tested R loc EF Q 10o/c V-3T4 FCV-700 AIR SAMPLE POST LOCA SUP 46-C 2 A 3/8 GL S C PI 2Y NA V-682B Tested R ISOL OC LT i C V-682B Tested R EF Q I Oo/c V-3T4 RCV-I I PURGE EXHAUST ISOL IC 35-C 2 A 48 BV A C PI 2Y NA V-2Q LT 2Y* V-662 *Per Tech Spec EF CS 2c CS27 V-3T7 RCV-12 PURGE EXHAUST ISOL OC 34-C 2 A 48 BV A C PI 2Y NA V-2E2 LT 2Y* C V-662 *Per Tech Spec EF CS 2c CS27 V-3T7 9B26YL00.DOC 40MIS 66

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.0 REV 0 (2005)

ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 51 OF 52 COMPRESSED AIR SYSTEMS P& ID NO. 1020 25 VALVE VALVE P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC NUMBER DESCRIPTION COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO. REMARKS AIR-S-114 CONT SERV AIR SUP ISOL IC 41-D 2 A,C 3 CK N C LT J c V-656 Tested R EC R c R03 V-656 (45-B) EP R 0 R03 V-656 AIR-S-200 CONT SERV AIR SUP ISOL OC 42-D 2 A 3 BA M LC LT 3 c V-656 PASSIVE (43-B) Tested R AIR-1-585 CONT NORM INST AIR SUP 42-C 2 A 1.5 DI M LC LT J c V-654 PASSIVE ISOL BYPASS OC (43-C) Tested R AIR-I-587 CONT NRM INST AIR SUP CK IC 42-D 2 A,C 2 CK N 0 LT R c V-654 Tested R (44-B) EC R c R03 V-654 EP R 0 R03 V-654 FCV-584 CNT NRM INST AIR SUP ISO OC 42-C 2 A 2 BA A 0 Pi 2Y NA V-2J7 (44-C) LT c V-654 Tested R EF Q lOc V-3S4 9B26YL00.DOC 40MIS 67

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ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) PAGE 52 OF 52 REMARKS

1. 1 The open safety function of check valves listed below are verified during normal operations at the frequencies noted per ISTC-3550.

Valve # Valve Description Procedure # Frequency FW-367 Main Feedwater to SG#2 Check STP R-2B2 Daily FW-368 Main Feedwater to SG# I Check STP R-2B2 Daily FW-531 Main Feedwater to SG#3 Check STP R-2B2 Daily FW-532 Main Feedwater to SG#4 Check STP R-2B2 Daily RCS-8046 Primary Water to PRT OP A-4B:I Refueling Outage RCS-8047 Nitrogen to PRT OP A-4B:I Refueling Outage CVCS-8440 VCT Outlet Check Valve STP P-CCP Quarterly CVCS-8367A-D RCP Seal Injection Inlet Check STP M-54 Monthly CVCS-8368A-D RCP Seal Injection Inlet Check STP M-54 Monthly CVCS-8372A-D RCP Seal Injection Inlet Check STP M-54 Monthly SI-8916 Nitrogen Supply to the Accumulators OP B-3B:I Refueling Outage CCW-585 CCW to Reactor Coolant Pumps and OP F-2:I Refueling Outage Rx Vessel Support Cooler (IC) OP A-6:1 CCW-695 CCW to Excess Letdown HX (OC) OPL-1 & Refueling Outage OP B-IA:IV LWS-60 Nitrogen to RCDT Check Valve (IC) OP G-l:VI Refueling Outage VAC-1 16 Containment Air Post Accident STP G-14 Refueling Outage Sample Return Check Valve (IC)

1. f2 The leak tests for valves FW-367,368, 531, and 532, are not required by Code as these valves do not have a safety related function to prevent back leakage. The leak test and the categorization as "A,C" is based on a corrective action in NCR DC 1-91 -TN-N002.

1. 3 FCV-1 IOA does not have an active safety function. The safety related boration flow path is through 8104 and the redundant flow path is from the RWST. However, in the Appendix R and Hosgri evaluations credit was taken for this valve to open or fail open so this valve is being administratively included in the IST program as a conservative measure since it may be considered a licensing commitment.

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 9B26YL00.DOC 40MIS 68

INSERVICE TESTING PROGRAM PLAN PUMPS AND VALVES TABLE 2.1 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE I OF 27 NO. V-CS1 Valves: FW-367 Steam Generator #2 Main Feedwater Check FW-368 Steam Generator #I Main Feedwater Check FW-531 Steam Generator #3 Main Feedwater Check FW-532 Steam Generator #4 Main Feedwater Check Catetorv: A/C Code Class: 2 Valves: FCV-438 Steam Generator #I Feedwater Isolation Valve FCV-439 Steam Generator #2 Feedwater Isolation Valve FCV-440 Steam Generator #3 Feedwater Isolation Valve FCV-441 Steam Generator #4 Feedwater Isolation Valve Category: B Code Class: 2 Function:

The check valves have an active function to close to prevent backflow so that AFW pump discharge flow will be directed to the steam generators as required when the AFW system is actuated.

The isolation valves have an active safety function to close to terminate continued feedwater flow to the steam generators or to a faulted feedwater line inside containment as assumed in the plant accident analysis.

Basis:

These Main Feedwater Check Valves and Feedwater Isolation Valves cannot be exercised during power operation because closing these valves would require securing feed flow to a steam generator which would result in a reactor trip.

Part stroking is not considered practical because of the risk of full closure. The risk is recognized in DCPP's Technical Specification Bases Document for Technical Specifications Surveillance Requirements 3.7.3.1 and 3.7.3.2, which states "These surveillances are normally performed upon returning the unit to operation following a refueling outage. These valves should not be tested at power since even a part stroke exercise increases the risk of a valve closure with the unit generating power."

Justification:

Cold shutdown frequency testing is per ISTC- 3522(b) and ISTC-3521(c).

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COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 2 OF 27 NO. V-CS2 Valves: FW-369 Aux Feedwater Pump #I to Steam Generator #1 Check Valve FW-370 Aux Feedwater Pump #2 to Steam Generator #I Check Valve FW-371 Aux Feedwater Pump #I to Steam Generator #2 Check Valve FW-372 Aux Feedwater Pump #2 to Steam Generator #2 Check Valve FW-373 Aux Feedwater Pump #I to Steam Generator #3 Check Valve FW-374 Aux Feedwater Pump #3 to Steam Generator #3 Check Valve FW-375 Aux Feedwater Pump #I to Steam Generator #4 Check Valve FW-376 Aux Feedwater Pump #3 to Steam Generator #4 Check Valve Catef!orT: C Code Class: 2 Function:

These valves have an active safety function in the open direction to permit the flow of water from the AFW pump discharge lines to the steam generators. Second off check valves FW-369, FW-370, FW-371, FW-372, FW-373, FW-374, FW-375, and FW-376 also have a safety function to close to prevent the backflow of feedwater through an idle AFW pump.

Basis:

These Auxiliary Feedwater Supply Check Valves cannot be full stroke exercised during power operation because the only available flow path is into the steam generators which could result in thermal shock to the associated piping and fittings. These valves will be full stroke exercised during a shutdown to, or a startup from, a cold shutdown condition.

Justification:

Cold shutdown frequency testing is per ISTC-3522(b).

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PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 3 OF 27 NO. V-CS3 Valves: FCV-41 Steam Generator #I Main Steam Isolation Valve FCV-42 Steam Generator #2 Main Steam Isolation Valve FCV-43 Steam Generator #3 Main Steam Isolation Valve FCV-44 Steam Generator #4 Main Steam Isolation Valve Cateeory: B Code Class: 2 Function:

These valves have an active safety function to automatically close on high steam flow, coincident with either low-low T(avg) or low steam pressure, or on a high-high containment pressure signal.

Basis:

These valves cannot be full stroke exercised during power operation because this would require securing steam from a steam generator which would result in a reactor trip, and most likely a safety injection.

Part stroke testing capability does exist for these valves but is not considered practical, since extremely limited (60 max., 20 nominal) valve motion is allowed due to the valve design which only provides verification that the valve is not frozen in the open position. Additionally, as a result of the valve design, performing partial stroke testing exposes the plant to an inadvertent Reactor Trip and/or Safety Injection should the valve stroke more than 60 (resulting in a flow assisted closure of the valve).

These valves will be full stroke exercised on a cold shutdown frequency.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

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COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 4 OF 27 NO. V-CS4 Valves: LCV-1 12B Volume Control Tank Outlet Isolation Valve LCV-1 12C Volume Control Tank Outlet Isolation Valve Catetorv: B Code Class: N/A Function:

These valves have an active safety function to close to isolate the volume control tank from the suction of the charging pumps upon the receipt of a safety injection signal.

Basis:

These isolation valves should not be full or part stroke exercised during power operation because failure of either valve in the closed position would result in a loss of reactor system level control or injecting 2000 ppm boric acid solution from the RWST into the reactor coolant system, resulting in a possible plant shutdown. See also NRC SER dated 1/31/94 addressing LA 86 and 87.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

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COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 5 OF 27 NO. V-CS5 Valves: 8100 Reactor Coolant Pump Seal Water Return Isolation Valve, Outside Containment 8112 Reactor Coolant Pump Seal Water Return Isolation Valve, Inside Containment Categorv: A Code Class: 2 Function:

These valves have an active safety function to close to isolate the seal water return line containment penetration upon receipt of a Phase A containment isolation signal.

Basis:

These isolation valves cannot be exercised during power operation because this would challenge the relief valve in the RCP seal water return line. If this relief valve failed in the open position, this would result in unnecessary reactor coolant system leakage.

These motor operated valves cannot be part stroke tested because the control system does not allow for part stroke testing.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

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COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 6 OF 27 NO. V-CS6 Valves: 8105 Centrifugal Charging Pumps' Recirculation Isolation Valve 8106 Centrifugal Charging Pumps' Recirculation Isolation Valve Cateiorv: B Code Class: 2 (8106), N/A (8105)

Function:

These valves have an active safety function to close to isolate the high pressure safety injection flow path from the CVCS during safety injection system operation following a LOCA.

Basis:

These valves should not be exercised during power operation because failure of either valve in the closed position could result in pump damage if a secondary system accident occurred.

These motor operated valves cannot be part stroke tested because the Bases for Technical Specification Surveillance Requirements 3.5.2.1 and 3.5.2.2 require that these valves be maintained open.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

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COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 7 OF 27 NO. V-CS7 Valves: 8107 Charging Line Isolation Valve 8108 Charging Line Isolation Valve Categorv: B Code Class: 2 Function:

These redundant, motor-operated gate valves have an active safety function to close to isolate the normal charging flow path from the high pressure safety injection flow path upon receipt of a safety injection signal.

Basis:

These valves should not be full stroke exercised during power operation because failure of either valve in the closed position could result in loss of reactor coolant system level control, which could result in a plant shutdown. The control scheme for these motor operated valves does not allow for part stroking. Also, failure of either of these valves in a closed position would place the plant in an LCO action statement due to a loss of the boration flow path from the boric acid tanks. See also NRC SER dated 1/31/94 addressing LA 86 and 87.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

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PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS 1 & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 8 OF 27 NO. V-CS8 Valves: 8145 Pressurizer Auxiliary Spray Valve 8148 Pressurizer Auxiliary Spray Bypass Valve Cateeorv: B Code Class: 1 Function:

Air operated globe valves 8145 and 8148, have an active safety function to open during plant cooldown to cooldown the pressurizer when normal pressurizer spray is inoperable. This is not an accident mitigation function but a safe shutdown function following a Hosgri earthquake.

Basis:

These valves should not be full stroke exercised during power operation because failure of eithervalve in the open position could result in a loss of reactor coolant system pressure control which could result in a plant shutdown. The control scheme for these air-operated valves does not allow for part stroking.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

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PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 9 OF 27 NO. V-CS9 Valves: 8146 Normal Charging 8147 Alternate Charging Cateeorv: B Code Class: 2 Function:

These valves have active functions to open to supply normal and alternate charging to Loop 4 or 3 RCS Cold Legs.

Basis:

These valves should not be full stroke exercised during power operation because this would cause a thermal transient to be induced on the charging to RCS Cold Leg nozzle. This is per Westinghouse Infogram (WIG)90-025. The control scheme for these air-operated valves does not allow for part stroking.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

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COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 10 OF 27 NO. V-CS10 Valves: 8149A Letdown Orifice Control/lsolation Valve 8149B Letdown Orifice Control/Isolation Valve 8149C Letdown Orifice Control/Isolation Valve Cateaorv: A Code Class: 2 Function:

These air operated globe valves have an active safety function to close to provide containment isolation and to isolate a high energy letdown line break outside containment upstream of the letdown heat exchanger.

Basis:

These valves will not be full stroke exercised during power operation due to the following causes: thermal transients on the regenerative letdown heat exchanger, hydraulic transients on the letdown line; pressure control transients resulting in the lifting of relief valve RV-8117; and charging nozzle temperature transients when charging is isolated during letdown testing. Reference NRC SER dated 1/31/94 addressing LA 86 and

87. The control scheme for these air-operated valves does not allow for part stroking.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

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PACIFIC GAS & ELECTRIC COMPANY PLDIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 11 OF27 NO. V-CS11 Valves: 8152 Letdown Line Isolation Valve, Outside Containment Category: A Code Class: 2 Function:

This air operated globe valve has an active safety function to close to isolate letdown on a high room temperature in the letdown heat exchanger room. This valve also has the safety function of providing containment isolation.

Basis:

This valve should not be full or part stroke exercised during power operation because failure of the valve in the closed position could result in a loss of reactor coolant system level control which could result in a plant shutdown. See also NRC SER dated 1/31/94 addressing LA 86 and 87. The control scheme for this air-operated valve does not allow for part stroking.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

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COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 12 OF 27 NO. V%-CS12 Valves: 8802A Safety Injection Pump #1 Discharge Isolation Valve, Outside Containment 8802B Safety Injection Pump #2 Discharge Isolation Valve, Outside Containment Cateaorv: A Code Class: 2 Function:

These motor operated gate valves have an active safety function to open to provide a flow path for the safety injection pumps in the Hot Leg recirculation mode.

Basis:

These valves cannot be full or part stroke exercised during power operation because they are required to be closed with power to the valve operators removed by Technical Specification SR 3.5.2.1. If these valves were opened during power operation and an accident were to occur, safety injection flow would go to the hot legs instead of the cold legs. The safety analysis has analyzed for flow going to the cold legs and not the hot legs.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

9B26YL00.DOC 40MIS 80

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 13 OF 27 NO. V-CS13 Valves: 8805A Charging Pump Suction Valve 8805B Charging Pump Suction Valve Catelory: B Code Class: 2 Function:

These motor operated gate valves have an active safety function to open to provide a flow path from the refueling water storage tank to the suction of the charging pumps.

Basis:

These valves should not be full or part stroke exercised at power because opening these valves injects highly oxygenated, 2000 ppm borated water from the RWST into the reactor coolant system. Injecting this water results in a negative reactivity addition to the reactor coolant system which could shut the plant down. See also NRC SER dated 1/31/94 addressing LA 86 and 87.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

9B26YL00.DOC 40MIS 81

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 14 OF 27 NO. V-CS14 Valves: 8808A SI Accumulator 1 Discharge Isolation 8808B SI Accumulator 2 Discharge Isolation 8808C SI Accumulator 3 Discharge Isolation 8808D SI Accumulator 4 Discharge Isolation Catezorv: B Code Class: 2 Function:

These valves are open with power removed from the valve operator during power operations. They are not required to operate during an accident requiring ECCS injection. Valves can be closed to prevent accumulator injection during normal cooldown/depressurization of RCS.

Basis:

These valves cannot be full or part stroke exercised during power operation because Technical Specification SR 3.5.1.1 and SR 3.5.1.5 require that accumulator discharge isolation valves remain open with power removed.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

9B26YL00.DOC 40MIS 82

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS 1 & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 15 OF 27 NO. V-CS15 Valves: 8809A RHR to Cold Legs 1&2 Isolation Valve 8809B RHR to Cold Legs 3&4 Isolation Valve Categori: B Code Class: 2 Function:

These motor operated gate valves have an active safety function to close during hot leg recirculation. These valves are exempt from type C leak testing per Appendix J, section III.C.3. They also have a passive safety function to remain open to provide a flow path from the RHR system to the SIS/RCS cold leg injection lines.

These valves are normally open with the power to the actuators removed during power operations.

Basis:

These valves cannot be full or part stroke exercised during power operation because they are required to be open with power to the valve operators removed by Technical Specification SR 3.5.2.1.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

9B26YL00.DOC 40MIS 83

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWVER PLANT - UNITS I & 2 PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT UNITS 1 & 2 -

INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 16 OF 27 NO. V-CS16 Valves: 8835 Safety Injection to Cold Legs Isolation Valve Catcorv: B Code Class: 2 Function:

This motor operated gate valve has an active safety function to close when placing the ECCS in the hot leg recirculation mode of safety injection. This valve is exempt from type C leak testing per Appendix J, section III.C.3.

Basis:

This valve cannot be full or part stroke exercised during power operation because it is required to be open with power to the valve operator removed by Technical Specification SR 3.5.2.1. Also, failure of this valve in the closed position would result in the safety injection system being not OPERABLE.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

9B26YL00.DOC 40MIS 84

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 17 OF 27 NO. V-CS17 Valves: 8974A Safety Injection Pumps Recirculation to the Refueling Water Storage Tank Isolation Valve 8974B Safety Injection Pumps Recirculation to the Refueling Water Storage Tank Isolation Valve Cateiom: B Code Class: 2 (8974B), N/A (8974A)

Function:

These motor operated globe valves have an active safety function to close via an interlock prior to either 8804A or 8804B opening.

Basis:

These valves cannot be full or part stroke exercised during power operation because they are required to be open with power to the valve operators removed by Technical Specification SR 3.5.2.1. Also, the failure of one of these valves in the closed position could result in damage to the safety injection pumps, if an SI signal were to start the pumps during this condition or test, thereby rendering the safety injection system not OPERABLE.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

9B26YL00.DOC 40MIS 85

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 18 OF 27 NO. V-CS18 Valves: 8976 RWST to Safety Injection Pumps Suction Isolation Valve Categorv: B Code Class: 2 Function:

This motor operated gate valve has an active safety function to close to prevent backflow to the refueling water storage tank during the post-LOCA recirculation mode of safety injection.

Basis:

This valve cannot be full or part stroke exercised during power operation because it is required to be open with power to the valve operator removed by Technical Specification SR 3.5.2.1. Also, failure of this valve in the closed position would result in the entire safety injection system being not OPERABLE.

Justification:

Cold shutdown frequency testing is per ISTC-352 I(c).

9B26YL00.DOC 40MIS 86

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 19 OF 27 NO. V-CS19 Valves: 8980 RWST to RHR Pumps Suction Isolation Valve Cateeorv: B Code Class: 2 Function:

This motor operated gate valve has an active safety function to close to prevent backflow into the refueling water storage tank if the downstream check valve leaks.

Basis:

This valve cannot be full or part stroke exercised during power operation because it is required to be open with power to the valve operator removed by Technical Specification SR 3.5.2.1. Also, failure of this valve in the closed position would result in the RHR portion of the safety injection system being not OPERABLE.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

9B26YL00.DOC 40MIS 87

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS 1 & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 20 OF 27 NO. V-CS20 Valves: 8701 RCS Loop 4 to RHR Isolation Valve 8702 RCS Loop 4 to RHR Isolation Valve Cateiory: A Code Class: I Function:

The motor operated double disc gate valves isolate the low pressure Residual Heat Removal System from the High Pressure Reactor Coolant System.

Basis:

These Reactor Coolant System to RHR System Isolation Valves cannot be full or part stroke exercised during power operation because they are required to be closed with power to the valve operators removed by Technical Specification SR 3.5.2.1. Also, failure of this valve to the open position would result in diversion of flow from the analyzed flow paths.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

9B26YL00.DOC 40MIS 88

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS 1 & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

COLD SH1UTDOWN FREQUENCY JUSTIFICATION PAGE 21 OF27 NO. V-CS21 Valves: 8703 RHR to Hot Legs Isolation Valve Catejorv: A Code Class: 2 Function:

This motor operated gate valve has an active safety function to open to provide a flow path for hot leg recirculation after a postulated accident. This valve is an RCS high pressure to low pressure interface boundary and is therefore leak rate tested every refueling outage per Tech Spec SR 3.4.14.1.

Basis:

This valve cannot be full or part stroke exercised during power operation because it is required to be closed with power to the valve operator removed by Technical Specification SR 3.5.2.1. Also, failure of this valve in the open position would result in diversion of flow from the analyzed flow paths.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

9B26YL00.DOC 40MIS 89

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - U)NITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 22 OF 27 NO. V-CS22 Valves: 8716A RHR Train Crosstie Valves 8716B RHR Train Crosstie Valves Category: B Code Class: 2 Function:

These motor operated gate valves have an active safety function to close to go to the cold leg mode of post-LOCA safety injection. They also have an active safety function to reopen to go to the hot leg mode of post-LOCA safety injection (no stroke time requirement). These valves are exempt from type C leak testing per Appendix J, section III.C.3.

Basis:

These valves cannot be part or full stroke exercised during power operation because closing one of these valves prevents RHR flow to 2 of 4 RCS loops which is not an analyzed condition. NRC IE Infonnation Notice 87-01 and DCPP Technical Specification Bases 3.5.2 require that these valves be maintained in the open position during power operations.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

9B26YL00.DOC 40MIS 90

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 23 OF 27 NO. V-CS23 Valves: 8742A RHR Heat Exchanger #I Discharge Check Valves 8742B RHR Heat Exchanger #2 Discharge Check Valves Catceorv: C Code Class: 2 Function:

These check valves have an active safety function to open to pass RHR flow from the RHR heat exchanger to the RCS. They also have a safety function to close (back flow) to prevent pump to pump interaction.

Basis:

These valves cannot be exercised during power operation because the RHR pumps do not develop sufficient head to overcome reactor coolant system pressure. These valves will be tested for backflow and for opening on a cold shutdown frequency.

Justification:

Cold shutdown frequency testing is per ISTC-3522(b).

9SB26YLOO.DOC 40MIS 91

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 24 OF 27 NO. V-CS24 Valves: 8994A NaOH to Containment Spray Eductor Isolation Valve 8994B NaOH to Containment Spray Eductor Isolation Valve Cateiory: B Code Class: 2 Function:

These motor operated gate valves have an active safety function to open to provide a flow path during the ECCS injection phase of containment spray and then during the ECCS recirculation phase up until the time that the RWST low-low level is reached.

Basis:

These valves cannot be part or full stroke exercised during power operation because they could introduce NaOH into the RWST and subsequently into the reactor coolant system causing Na24 activation problems and possible chemical damage to components in the reactor coolant system. To prevent getting NaOH into the RWST, valve 8992 would have to be closed and the line flushed, which would result in the entire Spray Additive System being not OPERABLE.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

9B26YL00.DOC 40MIS 92

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS 1 & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 25 OF 27 NO. V-CS25 Valves: FCV-355 Component Cooling Water Header C Isolation Valve Categorv: B Code Class: 3 Valves: FCV-356 CCW to RCP and Reactor Vessel Support Isolation Valve FCV-357 RCP Thermal Barrier CCW Return Isolation Valve FCV-363 RCP Cooler CCW Return Isolation Valve FCV-749 RCP Cooler CCW Return Isolation Valve FCV-750 RCP Thermal Barrier CCW Return Isolation Valve Catcory: A Code Class: 2 Function:

FCV-355 has an active safety function to close to isolate the non-vital CCW header C after an accident to assure adequate flow to the two vital CCW loops.

FCV-356, 357, 363, 749, and 750 each have an active safety function to close to provide containment isolation.

Basis:

These valves cannot be exercised during power operation because this could result in damage to the reactor coolant pumps and a possible plant trip.

These motor operated valves cannot be part stroke tested because the control system does not allow for part stroke testing.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

9B26YL00.DOC 40MIS 93

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS.l & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 26 OF 27 NO. V-CS26 Valves: FCV-696 Reactor Cavity Sump Sample Supply Isolation Valve FCV-697 Reactor Cavity Sump Sample Supply Isolation Valve FCV-235 Containment H2 Sample Supply Isolation Valve FCV-236 Containment H2 Sample Supply Isolation Valve FCV-237 Containment H2 Sample Return Isolation Valve FCV-238 Containment H2 Sample Supply Isolation Valve FCV-239 Containment H2 Sample Supply Isolation Valve FCV-240 Containment H2 Sample Supply Isolation Valve FCV-658 Containment H2 Purge Exhaust System #2 Suction Iso Valve FCV-659 Containment H2 Purge Exhaust System #1 Suction Iso Valve FCV-668 Containment H2 Purge Exhaust System #2 Suction Iso Valve FCV-669 Containment H2 Purge Exhaust System #1 Suction Iso Valve Category: A Code Class: 2 Function:

These valves have a passive safety function to remain closed to provide containment isolation.

Basis:

These Containment Sample Isolation Valves cannot be part or full stroke exercised during power operation because Technical Specification SR 3.6.3.3 and SR 3.6.3.4 requires these valves to be closed when containment integrity is required, except under strict administrative control. These valves do not receive a containment isolation signal.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

9B26YL00.DOC 40MIS 94

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.1 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

COLD SHUTDOWN FREQUENCY JUSTIFICATION PAGE 27 OF 27 NO. V-CS27 Valves: FCV-660 Containment Purge Supply Isolation Valve (IC)

FCV-661 Containment Purge Supply Isolation Valve (OC)

RCV-1 I Containment Purge Exhaust Isolation Valve (IC)

RCV-12 Containment Purge Exhaust Isolation Valve (OC)

Catelory: A Code Class: 2 Function:

These valves have an active safety function to provide containment isolation.

Basis:

These valves are required to be leakrate tested every time they are exercised per Technical Specification (Tech Spec) SR 3.6.3.7. These valves are administratively maintained in their isolation (closed) position during power operations. This ensures they will perform their required safety function and eliminates concerns regarding failure of a post-exercising leak test.

These valves will be full stroke exercised on a cold shutdown frequency.

Justification:

Cold shutdown frequency testing is per ISTC-3521(c).

9B26YL00.DOC 40MIS 95

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE I OF 27 NO. V-RO1 Valves: MS-1068, Steam Generator #1 Main Steam Line Check Valve MS-2066, Steam Generator #2 Main Steam Line Check Valve MS-3062, Steam Generator #3 Main Steam Line Check Valve MS4062, Steam Generator #4 Main Steam Line Check Valve Category: C Code Class: N/A Function:

These check valves have an active safety function to close in the event of a steam line break upstream of the main steam isolation valves. This accident mitigation function is to prevent the blowing down of more than one steam generator.

Basis:

These valves cannot be exercised closed because provisions are not provided in the plant design to verify that these valves close on reverse flow. Therefore, each refueling outage, one of these valves will be disassembled, mechanically exercised and examined on a refueling outage rotational frequency such that one valve shall be disassembled and examined each refueling outage; all four valves shall be disassembled and examined at least once every 8 years.

Basis for Check Valve Sample Disassembly Examination Program:

These check valves are of the same manufacturer, model number, size, orientation and service. They also have similar maintenance and modification histories. Since they are the main steam line check valves, they will be full stroke opened by steam flow from the steam generators during power ascension after each refueling outage.

Justification:

Refueling outage frequency testing is per ISTC-522 I(c)(3).

9B26YL00.DOC 40MIS 96

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 2 OF 27 NO. V-RO2 Valves: MS-5166, SG-2 Steam to Auxiliary Feedwater Pump #1 Check Valve MS-5 167, SG-3 Steam to Auxiliary Feedwater Pump #1 Check Valve Category: C Code Class: 2 Function:

These check valves function to supply steam to the turbine driven auxiliary feedwater pump. The valves also have a safety function in the closed (reverse-flow) position to prevent an intact steam generator from blowing down to containment through the turbine driven AFW pump steam supply line following a MSLB.

Basis:

Full stroke opening is verified on a cold shutdown basis when full flow pump test of turbine driven auxiliary feedwater pump is performed, but valve reclosure capability cannot be verified.

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation. There are no test connections or taps installed that would allow reverse-flow seating verification for these check valves. Alternatively, the ability of the valve to close following actuation will be verified by disassembly and internal inspection on a rotational basis, one valve each refueling outage not to exceed an eight year interval between disassembly and inspections for each valve. If any degradation is detected that interferes with the valve's operability, then the opposite train valve will also be disassembled and internally inspected during the same outage.

• Basis for Check Valve Sample Disassembly Examination Program:

These check valves are of the same manufacturer, size, orientation and service. Unit two valve MS-2-5 167 is essentially the same model as MS-1-5 166, MS-1-5 167 and MS-2-5 166, the only difference being that the equalizing line is orientated on the near side instead of the far side when viewing the valve from the side with flow going from the right to left. They also have similar maintenance and modification histories. Since they are the main steam supply to the turbine driven auxiliary feedwater pump, they will be full stroke opened by steam flow when full testing the auxiliary feedwater pump after each refueling outage.

Justification:

Rotational Refueling outage frequency testing is per ISTC-5221(c)(3).

9B26YL00.DOC 40MIS 97

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2

• ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 3 OF 27 NO. V-RO3 Valves:

AXS-208 Auxiliary Steam Supply to Containment (IC) 8046 Primary Water to PRT Isolation (IC) 8047 Nitrogen to PRT Isolation Check (IC) 8368A RCP-I Seal Injection First Check (IC) 8368B RCP-2 Seal Injection First Check (IC) 8368C RCP-3 Seal Injection First Check (IC) 8368D RCP4 Seal Injection First Check (IC) 8916 Nitrogen Supply to Accumulator Isolation Check (IC)

CCW-585 CCW to RCP & RX Vessel Support Check (IC)

CCW-695 CCW to Excess Letdown HX Check (OC)

LWS-60 Nitrogen to RCDT Isolation Check (IC)

VAC-1 16 Containment Air Sample Post-LOCA Return Isolation Check (IC)

AIR-I-587 Containment Normal Instrument Air Supply Isolation Check (IC)

AIR-S-1 14 Containment Service Air Supply Isolation Check (IC)

A, C Code Class: 2 Function:

These check valves serve as containment isolation valves and have the safety function to close to prevent back leakage from containment to system outside of containment. These valves do not have an open safety function.

Basis:

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation. They are located inside containment.

These containment isolation valves can only be verified closed by performing a seat leakage test.

Performance of seat leakage test can not be performed during power operation because it would require breaching containment, setting up test equipment inside containment and personnel would be required to enter containment to perform necessary valve alignments and test equipment setup.

It is impracticable to stroke test these valves during cold shutdown because the only test method to verify closure is to perform a seat leakage test. Personnel would be required to enter containment to perform valve alignments and setup of test equipment for the leak test.

Open stroke tests for these valves need not be performed at an interval when it is not practicable to perform the check valve closure test per ISTC-3522(a).

Justification:

Refueling outage frequency testing is per ISTC-3522(c).

9B26YL00.DOC 40MIS 98

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 4 OF 27 NO. V-RO4 Valves: 8078A Reactor Vessel Head Vent Valve 8078B Reactor Vessel Head Vent Valve 8078C Reactor Vessel Head Vent Valve 8078D Reactor Vessel Head Vent Valve Catejory: B Code Class: 2 Function:

These valves have an active function to open to vent noncondensible gases from the RCS, which might inhibit core cooling during natural circulation. They were installed to provide reactor vessel high point vent capability for beyond-design-bases events per the guidance of NUREG 0737 and are not relied upon to mitigate any design basis accidents as defined and analyzed in the FSAR Chapter 15 Accident Analyses.

Basis:

These Reactor Vessel Head Vent Valves should not be full or part stroke exercised during power operation by NRC direction.

Stroke time testing of the Reactor Vessel Head Vent Valves during Cold Shutdown has resulted in borated water from the valves to drip onto the Reactor Vessel Head. The borated water could cause corrosion damage to the Reactor Vessel Head. During Refueling Outages special test equipment is set up inside the Containment Building to flush the Reactor Vessel Head Vent Valves and piping with demineralized water after the stroke tests are complete. Setting up the special test equipment inside containment is impractical during Cold Shutdown forced outages, because the Reactor Vessel head is inaccessible and there would be significant radiation exposure to personnel.

Justification:

Refueling Outage frequency testing per ISTC-3521 (e).

9B26YL00.DOC 40MIS 99

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 5 OF 27 NO. V-RO5 Valves: CCW-581, FCV-749 Bypass Check Valve CCW-670, FCV-750 Bypass Check Valve CVCS-8109 8112 Bypass Check Valve Cateiorv: A,C Code Class: 2 Function:

The Bypass Check Valves have a safety function in the open direction of protecting the containment penetrations from over pressurization from thermal expansion of the liquid trapped between the containment isolation valves after an accident that results in an increase in containment temperature. These valves need to only partially open a small amount to fulfill this function. They also serve as containment isolation valves, so they have a safety function in the closed direction to prevent back leakage.

Basis:

These Bypass Check Valves cannot be exercised during power operation because the test would require clearing the reactor coolant pumps which are required for power operations. The tests also require that test equipment be set up inside the containment building.

These valves cannot be tested during cold shutdown because the test requires setting up test equipment inside containment, clearing reactor coolant pumps, and numerous valve manipulations.

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

Justification:

Refueling outage frequency testing is per ISTC-3522 (c). Seat leakage testing is the only method of verifying closure. Open stroke need only be performed at an interval when it is practicable to perform the closure test.

9B26YL00.DOC 40MIS 100

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 6 OF 27 NO. V-RO6 Valves: 8367A, RCP-I Seal Injection 2nd Check Valve 8367B, RCP-2 Seal Injection 2nd Check Valve 8367C, RCP-3 Seal Injection 2nd Check Valve 8367D, RCP4 Seal Injection 2nd Check Valve 8372A, RCP-I Seal Injection 3rd Check Valve 8372B, RCP-2 Seal Injection 3rd Check Valve 8372C, RCP-3 Seal Injection 3rd Check Valve 8372D, RCP4 Seal Injection 3rd Check Valve Cateiorw: C Code Class: I Function:

These valves are the RCS code pressure boundary valves on the RCP seal injection lines. The closing' function of these valves to protect the upstream piping from over pressurization is not considered to be a safety function, at least for the purposes of the IST program, because the upstream piping is designed for, and normally subjected to, pressure higher than RCS pressure. Hence the ability of these valves to close is not a required safety function. RCP seal cooling is considered to be a safety function because a failed seal is considered to be a small break LOCA. For a Main Steam Line Break inside containment, CCW flow to the RCP thermal barrier is isolated. Seal injection is then the only means of providing seal cooling and preventing seal failure. These valves must open to pass seal injection flow. Summary, these check valves have a safety function to open, but do not have a safety function to close.

Basis:

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

These check valves are required to be open during normal operation since this position provides normal seal flow to the RCP's. Therefore they cannot be stroked tested in the closed direction during operation of the plant.

These check valves cannot be stroke tested closed during cold shutdown operation because the test would require clearing the reactor coolant pumps, setting up test equipment inside the containment building and numerous valve manipulations. It is not practicable to perform these tests during cold shutdown.

Basis for Testing Series Check Valve Pairs as a Unit:

These valves are arranged so that there are two valves in series to each RCP. There are no test connections between the valves that would enable the valves to be individually tested. They will therefore be tested as pairs in accordance with ISTC-5223.

Therefore, each refueling outage, these valves will be verified closed by performing a backpressure flow test on each pair of valves.

Justification:

Refueling outage frequency testing is per ISTC-3522(c).

9B26YL00.DOC 40MIS 101

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS 1 & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 7 OF 27 NO. V-RO7 Valves: 8377 Pressurizer Auxiliary Spray Check Valve Categorv: C Code Class: I Function:

Check valve 8377, has an active safety function to open enable use of the auxiliary spray system for reactor shutdown when normal pressurizer spray is inoperable. This is not an accident mitigation function but a safe shutdown function following a Hosgri earthquake.

Basis:

This valve is not equipped with a mechanical exerciser, position indicator or differential pressure instrumentation. The valve is located inside containment.

A flow test of this valve during power operations would require that either air operated globe valve 8145 or 8148 be opened. Failure of either valve in the open position could result in a loss of reactor coolant system pressure control that could result in a plant shutdown.

This check valve cannot be stroke tested closed during cold shutdown operation because the test would require setting up test equipment inside the containment building and numerous valve manipulations. It is not practicable to perform this test during cold shutdown.

Justification:

Refueling outage frequency testing is per ISTC-3522(c).

9B26YL00.DQC 40MIS 102

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 8 OF 27 NO. V-RO8 Valves: 8378A Charging to Loop 3 Cold Leg Check 8378B Charging to Loop 4 Cold Leg Check 8379A Charging to Loop 3 Cold Leg Check 8379B Charging to Loop 4 Cold Leg Check Catefon: C Code Class: I Valves: 8378C Charging Line Check Catezorv: C Code Class: 2 Function:

8378A, 8378B, 8379A and 8379B are the RCS code pressure boundary valves on the RCP normal and alternate charging lines. The closing function of these valves to protect the upstream piping from over pressurization is not considered to be a safety function, at least for the purposes of the IST program, because the upstream piping is designed for, and normally subjected to, pressure higher than RCS pressure. Hence the ability of these valves to close is not a required safety function. These valves have active functions to open to supply normal and alternate charging to Loop 4 or 3 RCS Cold Legs for emergency boration flow path.

8378C is a containment isolation valve but is exempted from 10CFR50 Appendix J required leak rate testing. It has the same safety function to open as 8378A/B and 8379A/B.

Summary, these check valves have a safety function to open, but do not have a safety function to close.

Basis:

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation. They are located inside containment.

These valves should not be exercised during power operation because this would cause a thermal transient to be induced on the charging to RCS Cold Leg nozzle. This is per Westinghouse Infogram (WIG)90-025.

These check valves cannot be stroke tested closed during cold shutdown operation because the test would require setting up test equipment inside the containment building and numerous valve manipulations. It is not practicable to perform these tests during cold shutdown.

Justification:

Refueling outage frequency testing is per ISTC-3522(c).

9B26YL00.DOC 40MIS 103

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWDER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 9 OF 27 NO. V-RO9 Valves: 8440 Volume Control Tank Outlet Check Valve CategorV: C Code Class: 2 Function:

This check valve has an active safety function to close to prevent backflow from the charging pump suction header to relief valve 8123 during the post-LOCA containment sump recirculation mode of safety injection.

It also has a safety function to open to provide a flow path for the charging pump mini-flow recirculation to return to the suction header of the charging pumps.

Basis:

This valve is not equipped with a mechanical exerciser, position indicator or differential pressure instrumentation.

This check valve is open during operation to provide the normal source of supply to the suction of the charging pumps. Exercising this valve during power operation would require alignment to the alternate supply which would result in injecting highly oxygenated, 2000 ppm borated water into the reactor coolant system. Injecting this water results in a negative reactivity addition to the reactor coolant system which could shut the plant down.

This valve cannot be tested for backflow during power operation as the only acceptable method of testing would be to perform hydros and measure for backleakage. This testing would require clearing pumps, entering ACTION Statements, and numerous valve and pump manipulations which affect the pressurizer level control and letdown temperature. This can cause cavitation in the letdown line.

This valve cannot be tested for backflow during cold shutdown as the only acceptable method of testing would be to perform hydros and measure for backleakage. This testing would require clearing pumps, entering ACTION Statements, and numerous valve and pump manipulations along with setting up the hydro testing equipment. It is not practicable to perform this testing on a cold shutdown frequency, therefore the closure test will be performed on a refueling outage frequency.

The ability to open is proven during normal operations per ISTC-3550. Closure will be tested on a refueling outage frequency.

Justification:

Refueling outage frequency testing is per ISTC-3522(c) 9B26YL00.DOC 40MIS 104

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 10 OF 27 NO. V-RO10 Valves: 8445 Emergency Borate Reverse Flow Check Valve Categorm: C Code Class: 2 Function:

Check valve 8445, has an active safety function to open permit emergency boration flow through emergency borate valve 8104. It has no safety function in the closed direction.

Basis:

This valve is not equipped with a mechanical exerciser, position indicator or differential pressure instrumentation.

This check valve cannot be backflow tested during power operations because this test would require that both trains of boration flow path be cleared.

This check valve cannot be stroke tested closed during cold shutdown operation because the test would require clearing both trains of boration flow path, operating sealed closed valve, set up of test equipment and numerous valve manipulations. It is not practicable to perform this test during cold shutdown.

Justification:

Refueling outage frequency testing is per ISTC-3522(c).

9B26YL00.DOC 40MIS 105

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 11 OF 27 NO. V-ROll Valves: 8475 Positive Displacement Charging Pump Discharge Check Valve Category: C Code Class: 2 Function:

This valve has an active safety function to open to allow passage of the positive displacement charging pump's discharge flow. It also has a safety function of preventing backflow from another charging pump while the positive displacement charging pump is idle.

Basis: I This valve is not equipped with a mechanical exerciser, position indicator or differential pressure instrumentation.

Open stroke testing for 8475 will be performed quarterly.

This valve cannot be tested for backflow during power operation, as the only acceptable method of testing would be to perform hydros and measure for backleakage. This testing would require clearing pumps, entering ACTION statements, and numerous valve and pump manipulations which affect the pressurizer level control and letdown temperature. This can cause cavitation in the letdown line.

This valve cannot be tested for backflow during cold shutdown, as the only acceptable method of testing would be to perform hydros and measure for backleakage. This testing would require clearing pumps, entering ACTION statements, and numerous valve and pump manipulations, along with setting up the hydro testing equipment.

This valve will be tested for backflow each refueling outage.

Justification:

Refueling outage frequency testing is per ISTC-3522(c).

9B26YL00.DOC 40MIS 106

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 12 OF 27 NO. V-RO12 Valves: 8483, Charging Flow to Cold Legs Bypass Check Valve Category: C Code Class: I Function:

This valve has a safety function to open to relieve pressure build up if normal and alternate charging valves 8146 and 8147 are both closed and Regenerative Heat Exchanger added heat to the charging line with resulting thermal expansion and pressure increase. The valve need only to partially open and allow flow to perform its safety function. The valve does not have a safety function to close to prevent back flow.

Basis:

This check valve cannot be exercised during power operation because opening this valve would require closing normal and alternate charging valves 8146 and 8147 which would isolate normal charging. This would result in thermal transient to be induced in the charging to RCS Cold Leg nozzles. This is per Westinghouse Infogram (WIG 90-025).

This valve cannot be tested for flow during Cold Shutdown as the only acceptable method of testing is to isolate normal and alternate charging thus isolating charging flow. The resultant differential pressure seen by 8146 or 8147 would be extremely high because all of the charging pump pressure would have to be reduced at the normal or alternate charging valve which is not set up to accomplish this. The valve can be tested during refueling outages when charging pump full flow tests using charging injection flow path are performed. During the charging pump full flow tests, the pressures differential across the normal or alternate charging valves is much lower.

Justification:

Refueling outage frequency testing is per ISTC-3522(c).

9B26YL00.DOC 40MIS 107

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 13 OF 27 NO. V-RO13 Valves: 8487A Boric Acid Transfer Pump 2 Discharge Check Valve 8487B Boric Acid Transfer Pump I Discharge Check Valve Categorv: C Code Class: 2 Function:

These valves have the safety function of opening to allow the discharge of boric acid for emergency boration. The boric acid transfer pumps are normally aligned such that only one pump discharges to the boric acid filter, while the other is aligned to recirculate flow to back to the boric acid storage tank. To align the second pump to the common discharge line to the boric acid filter requires local manual operator action, at which time a second local manual isolation valve could be closed if necessary to prevent short circuiting of flow. Hence, operation of these check valves in the closed direction is not considered to be a safety function.

Basis:

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

These check valves cannot be backflow tested during power operations or cold shutdown because this test would require that at least one train of boration flow path be cleared, test equipment to be set up and numerous valves to be manipulated. The boric acid transfer system is heat traced to maintain temperature, clearance of this system could result in a long term inoperability of the system.

It is not practicable to perform this test during power operations or cold shutdown.

Justification:

Refueling outage frequency testing is per ISTC-3522(c).

9B26YL00.DOC 40MIS 108

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 14 OF 27 NO. V-RO14 Valves: 8804A, Charging Pump Suction from RHR System Isolation Valve 8804B, Safety Injection Pump Suction from RHR System Isolation Valve 9003A, RHR Hx-1 to containment spray header A Isolation Valve 9003B, RHR Hx-2 to containment spray header A Isolation Valve Cateiory: B Code Class: 2 Function:

These motor-operated gate valves have an active safety function to open. This will line up the safety injection system and the containment spray system for the cold leg recirculation phase of post-LOCA safety injection.

Basis:

These valves cannot be full or part stroke exercised during power operation because they are interlocked with valves 8982A&B (Containment Sump Isolation Valves) that are required to be closed with power to the valve operators removed by Technical Specification SR 3.5.2.1. Valves 8982A or B cannot be opened during power operation because this would result in one train of the RHR system being not OPERABLE.

During cold shutdown, valves 8804A & B and 9003A & B cannot be full or part stroke exercised open because they are interlocked with valve 8701 and 8702 (RCS Loop-4 TO RHR ISOLATION VALVES) in the closed position. 8701 and 8702 are required to be open and closing one of these valves would result in both RHR trains being incapable of removing decay heat from the core.

Valves 8804A&B and 9003A&B will be full stroke exercised during refueling outages.

Justification:

Refueling outage frequency testing is per ISTC-3521(e).

9B26YL00.DOC 40MIS 109

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 15 OF 27 NO. V-RO15 Valves: 8819A, Safety Injection to Cold Leg #I Check Valve 88198, Safety Injection to Cold Leg #2 Check Valve 8819C, Safety Injection to Cold Leg #3 Check Valve 8819D, Safety Injection to Cold Leg #4 Check Valve 8905A, Safety Injection to Hot Leg #1 Check Valve 8905B, Safety Injection to Hot Leg #2 Check Valve 8905C, Safety Injection to Hot Leg #3 Check Valve 8905D, Safety Injection to Hot Leg #4 Check Valve Cateporv: A,C Code Class: I Function:

These check valves have an active safety function to open to supply flow from the safety injection pumps to the reactor coolant system (RCS).

Basis:

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation. They are located inside containment.

These valves cannot be exercised during power operation because the safety injection pumps do not develop sufficient head to overcome RCS pressure.

These valves cannot be exercised during cold shutdown because a maximum of zero safety injection pumps are allowed to be capable of injecting into the RCS by Technical Specification SR 3.4.12.1 to protect against a low temperature overpressurization of the RCS. Also during cold shutdown there may not be sufficient volume in the RCS to accommodate the amount of water needed to full stroke exercise these valves.

These valves will be full stroke exercised during refueling outages.

Justification:

Refueling outage frequency testing is per ISTC-3522(c).

9B26YL00.DOC 40MIS 110

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 16 OF 27 NO. V-RO16 Valves: 8820, Charging Injection 2nd-off Check Valve 8900A, Charging Injection Loop-I Cold Leg Check Valve 8900B, Charging Injection Loop-2 Cold Leg Check Valve 8900C, Charging Injection Loop-3 Cold Leg Check Valve 8900D, Charging Injection Loop-4 Cold Leg Check Valve Cateaorv: C Code Class: I Function:

These check valves have an active safety function to open to supply safety injection flow to the reactor coolant system (RCS) cold legs from the high-head safety injection pumps (centrifugal charging pumps).

Basis:

These valves cannot be full stroke exercised during plant operation because the high RCS pressure will prevent the maximum required injection flow rate.

These valves cannot be full stroke exercised during cold shutdown because of insufficient RCS expansion volume to accommodate the high flow rates required to full stroke these valves. These high flow rates could challenge the RCS low temperature overpressure (LTOP) mitigation system. To prevent challenging the LTOP system, venting of the pressurizer by removal of a safety valve would be required. Additionally, full stroke exercising these valves cannot be performed with a bubble in the pressurizer, because the net charging rate must be minimal to prevent thermal cycling of the pressurizer.

These valves are not equipped with mechanical exercisers, position indicators, or differential pressure instrumentation.

These valves will be full stroke exercised on a refueling outage frequency.

Justification:

Refueling outage frequency testing is per ASME OM Code ISTC-3522(c).

9B26YL00.DOC 40MIS III

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2

• ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 17 OF 27 NO. V-RO17 Valves: SI-8919A Safety Injection Pump I to RWST Check Valve SI-8919B Safety Injection Pump 2 to RWST Check Valve Category: C Code Class: 2 Function:

These check valves have the safety function to open to enable functioning of the Safety Injection pump minimum flow system. These check valves do not have a safety function to close.

Basis:

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

These valves can only be verified closed by performing a seat leakage test using a hydrostatic pump.

Performance of seat leakage test cannot be performed during power operation because it would require closure of the SI Pump recirculation line motor operated valves, which are required by technical specifications to remain open during power operations.

It is impracticable to stroke closed these valves during cold shutdown because the only test method to verify closure is to perform a seat leakage test. Performance of this test requires setup of a hydrostatic pump and associated test equipment for the leak test. The system alignment would render both SI pumps inoperable because the recirculation line would be isolated.

Open stroke tests for these valves need not be performed at an interval when it is not practicable to perform the check valve closure test per ISTC-3522(a), therefore open stroke tests are also performed on a refueling outage frequency.

Justification:

Refueling outage frequency testing is per ISTC-3522(c).

9B26YL00.DOC 40MIS 112

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 18 OF 27 NO. V-RO18 Valves: 8922A, Safety Injection Pump #1 Discharge Check Valve 8922B, Safety Injection Pump f12 Discharge Check Valve Category: C Code Class: 2 Function:

These check valves have an active safety function to open to supply flow from the safety injection pumps to the reactor coolant system (RCS). They also have a closure safety function (backflow) to prevent pump to pump interaction.

Basis:

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

These valves cannot be exercised open during power operation because the safety injection pumps do not develop sufficient head to overcome RCS pressure.

These valves cannot be exercised open during cold shutdown because Technical Specification SR 3.4.12.1 requires that a maximum of zero safety injection pumps are capable of injecting into the RCS to protect against a low temperature overpressurization of the RCS. Also during cold shutdown there may not be sufficient volume in the RCS to accommodate the amount of water needed to full stroke exercise these valves.

These valves will be full stroked exercised open during refueling outages.

Justification:

Refueling outage frequency testing is per ISTC-3522(c).

9B26YL00.DOC 40MIS 113

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 19 OF 27 NO. V-RO19 Valves: 8924 RWST to Charging Pump Check Valve Category: C Code Class: 2 Function:

This check valve has an active safety function to open to supply borated water from the RWST to the suction of the Charging Pumps. This valve also has a safety function in the closed position (backflow) to limit potential post-LOCA recirculation flow to the RWST.

Basis:

The valve cannot be full stroked exercised during power operation because this would require injecting borated water from the RWST into the RCS, which could result in a plant shutdown.

The valve cannot be exercised during cold shutdown because of the high flow rates could challenge the RCS low temperature overpressure protection system.

Close exercising of valve 8924 is not practicable during power operation or cold shutdown because the test method used would require either the use of a hydro pump to pressurize the suction side of the charging pumps or opening of SI-8804A to pressurize the suction of the charging pumps using an RHR pump, neither of which can be performed when the plant is in cold shutdown. The valve is not equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

Valve 8924 can be full stroke tested each refueling outage.

Justification:

The valve shall be full stroke exercised during refueling outages per ISTC-3522(c) 9B26YL00.DOC 40MIS 114

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 20 OF 27 NO. V-RO20 Valves: 8949A, Safety Injection to Hot Leg #I Check Valve 8949B, Safety Injection to Hot Leg #2 Check Valve 8949C, Safety Injection to Hot Leg #3 Check Valve 8949D, Safety Injection to Hot Leg #4 Check Valve Catelory: A,C Code Class: I Function:

These check valves have an active safety function to open to supply safety injection flow to the reactor coolant system (RCS) hot legs.

Basis:

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation. They are located inside containment.

Valves 8949A&B cannot be exercised during power operation because neither the residual heat removal nor the safety injection pumps develop sufficient head to overcome RCS pressure. Valves 8949C&D cannot be exercised during power operation because the safety injection pumps do not develop sufficient head to overcome RCS pressure.

These valves cannot be exercised during cold shutdown because a maximum of zero safety injection pumps are capable of injecting into the RCS by Technical Specification SR 3.4.12.1 to protect against a low temperature over-pressurization of the RCS. Valves 8949A&B cannot be exercised during cold shutdown using the RHR pump because this would result in short cycling the core and not removing decay heat properly.

These valves will be full stroke exercised during refueling outages.

Justification:

Refueling outage frequency testing is per ISTC-3522(c).

9B26YL00.DOC 40MIS 115

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 21 OF 27 NO. V-RO21 Valves: 8977 RWST to Safety Injection Pump Check Valve Categorv: C Code Class: 2 Function:

This check valve has an active safety function to open to supply borated water from the RWST to the suction of the Safety Injection Pumps. This valve also has a safety function in the closed position (backflow) to limit potential post-LOCA recirculation leakage to the RWST.

Basis:

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation. They are located inside containment.

The valve cannot be full stroked exercised during power operation because the Safety Injection Pumps do not develop enough head to overcome RCS pressure.

The valve cannot be exercised during cold shutdown because a maximum of zero Safety Injection Pumps are allowed to be capable of injecting into the RCS per Technical Specification SR 3.4.12.1 to protect against a low temperature over pressurization of the RCS.

Close exercising of valve 8977 is not practicable during power operation or cold shutdown because the test method used would require either the use of a hydro pump to pressurize the suction side of the safety injection pumps or opening of SI-8804B to pressurize the suction of the safety injection pumps using an RHR pump, neither of which can be performed when the plant is in cold shutdown.

The valve is not equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

Valve 8977 can be full stroke tested each refueling outage.

Justification:

The valve shall be full stroke exercised during refueling outages per ISTC-3522(c).

9B26YLO0.DOC 40MIS 116

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 22 OF 27 NO. V-RO22 Valves: 8981 Refueling Water Storage Tank to Residual Heat Removal Pump Check Valve Category: C Code Class: 2 Function:

This check valve has an active safety function to open to supply borated water from the RWST to the suction of the RHR pumps. This valve also has a safety function in the closed position (backflow) to limit potential post-LOCA recirculation leakage to the RWST.

Basis:

The valve cannot be full stroked exercised during power operation because the RHR pumps do not develop enough head to overcome RCS pressure.

The valve cannot be exercised during cold shutdown because both RHR pumps must be aligned to remove decay heat from the RCS; therefore no flow path exists for full stroke exercising the valve. The valve is not equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

Valve 8981 will be full stroke exercised each refueling outage.

Valve 8981 will be back pressure tested close each refueling outage.

Justification:

The valve shall be full stroke exercised during refueling outages per ISTC-3522(c).

9B26YL00.DOC 40MIS 117

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 23 OF 27 NO. V-RO23 Valves: 8982A, Containment Recirc Sump to RHR Pump #1 Isolation Valve (Outside Containment) 8982B, Containment Recirc Sump to RHR Pump #2 Isolation Valve (Outside Containment)

Catepory: B Code Class: 2 Function:

These motor-operated gate valves have an active safety function to open which allows the RHR pumps to take suction from the containment recirculation sumps during the cold leg recirculation phase of an accident.

Basis:

These valves cannot be full or part stroked exercised during power operation because they are required to be closed with power to the valve operators removed by Technical Specification SR 3.5.2.1. If these valves were opened during power operation, this would result in one train of the RHR system being not OPERABLE.

These valves cannot be full or part stroke exercised during cold shutdown because opening one of these valves could introduce air into the suction piping of the RHR pumps, causing the RHR pumps to be not OPERABLE for an extended period of time.

These valves will be full stroke exercised on a refueling outage frequency.

Justification:

Refueling outage frequency testing is per ISTC-3521(e).

9B26YL00.DOC 40MIS 118

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 24 OF 27 NO. V-RO24 Valves: 8998A Spray Additive Tank Outlet Check Valve 8998B Spray Additive Tank Outlet Check Valve Categorv: A,C Code Class: 2 Function:

These check valves have an active safety function to open to allow the passage of sodium hydroxide solution for eduction into the containment spray flow. They also have a safety function to prevent back leakage, and thereby prevent diluting the educted NaOH solution, in the event that one of the containment spray pumps fails.

Basis:

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

These valves cannot be exercised during power operation because the system alignment for testing these check valves would result in the entire Spray Additive System being not OPERABLE.

These valves can only be verified closed by performing a seat leakage test. Performance of this test involves setting up of leak test equipment, breaching radioactive systems, aligning normally sealed valves and collecting radioactive fluids in leak measuring devices. The alignment would render both trains of containment spray system inoperable.

Open stroke tests for these valves need not be performed at an interval when it is not practicable to perform the check valve closure test per ISTC-3522(a), therefore the open stroke tests are also performed on a refueling outage frequency.

Justification:

Cold shutdown frequency testing is per ISTC-3522(c).

9B26YL00.DOC 40MIS 119

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 25 OF 27 NO. V-RO25 Valves: MU-971 Makeup Water to Miscellaneous Sources Check Valve Category: C Code Class: 3 Function:

These check valves have an active safety function to open to allow flow from the condensate storage tank via the makeup water transfer pumps to the spent fuel pool. MU-971 is in this flow path. Closure of this valve is not a safety function.

Basis:

This valve cannot be exercised during power operation or cold shutdown because the closure test uses a hydrostatic pump to back seat test the valve. This requires set up of test equipment inside the radiological controlled area, isolating and draining portions of the makeup water system that provide makeup water to the spent fuel pool, CCW surge tanks, chemistry lab sample sinks, condensate polishing demineralizers and the post loca sample room among other things.

Open stroke tests for this valve need not be performed at an interval when it is not practicable to perform the check valve closure test per ISTC-3522(a), therefore the open stroke test is also performed on a refueling outage frequency.

This valve is not equipped with a mechanical exerciser, position indicator or differential pressure instrumentation.

Justification:

Cold shutdown frequency testing is per ISTC-3522(c).

9B26YL00.DOC 40MIS 120

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2

• ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 26 OF 27 NO. V-RO26 Valves: FP-I 80 Containment Fire Water Isolation Check Valve (IC) - Unit One FP-867 Containment Fire Water Isolation Check Valve (IC) - Unit Two Category: A,C Code Class: 2 Function:

These check valves have the safety function in closed direction of preventing back leakage to maintain design basis containment integrity. The valves have no safety function in the open direction; the ability to provide firewater to the containment, while important, is not considered to be safety related.

Basis:

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation.

These valves can only be verified closed by performing a seat leakage test. Performance of seat leakage test can not be performed during power operation because it would a breach of containment integrity, require setting up test equipment inside containment and aligning the fire protection system in such a way that the containment fire protection header is isolated.

It is impracticable to stroke closed these valves during cold shutdown because the only test method to verify closure is to perform a seat leakage test. Performance of this test requires setup of test equipment and either isolating firewater to containment building or installing a firewaterjumper'to provide containment firewater flow during the time the header is isolated.

Open stroke tests using flow for these valves require that special fire hoses and headers be installed and routed to a spare containment penetration so that firewater flow can be directed outside containment. This alignment renders both the fire water system and containment integrity inoperable for the duration of the test and until an extensive amount of test equipment removed and plant systems restored. It is not practicable to perform the flow test in either plant operation or cold shutdown.

Therefore open stroke tests are performed on a refueling outage frequency.

Justification:

Refueling outage frequency testing is per ISTC-3522(c).

9B26YL00.DOC 40MIS 121

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS 1 & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.2 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REFUELING OUTAGE FREQUENCY JUSTIFICATION PAGE 27 OF 27 NO. V-RO27 Valves:

VAC-252 Containment Hydrogen Sample Return Isolation Check (IC)

VAC-253 Containment Hydrogen Sample Return Isolation Check (IC)

Cateiory: A, C Code Class: 2 Function:

These check valves serve as containment isolation valves and have the safety function to close to prevent back leakage from containment to system outside of containment. These valves have a safety function to open for containment hydrogen monitoring capability to complete the sample flow path from containment to the hydrogen monitors and back to the containment.

Basis:

These valves are not equipped with mechanical exercisers, position indicators or differential pressure instrumentation. They are located inside containment.

These containment isolation valves can only be verified closed by performing a seat leakage test.

Performance of seat leakage test can not be performed during power operation because it would require breaching containment, setting up test equipment inside containment and personnel would be required to enter containment to perform necessary valve alignments and test equipment setup.

It is impracticable to full stroke open test these valves using flow during power operations and cold shutdown because the hydrogen monitoring system flow indicator is not calibrated. During refueling outages, the portable leak test monitor is used to measure flow rate through the check valves as part of the local leak rate test procedure. This can only be performed during refueling outages.

Justification:

Refueling outage frequency testing is per ISTC-3522(c).

9B26YL00.DOC 40MIS 122

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - VALVES TABLE 2.3 ASME/OM-2001 (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE I OF 2 RELIEF REQUEST COMPONENT RELIEF REQUEST APPROVAL STATUS I Valves that cannot be stroke tested in Cold Shutdown unless Reactor Pre-Approved per NUREG-1482 Revision 1, paragraph 3.1.1.4.

Coolant Pump are shutdown.

CCW-FCV-355, CCW-FCV-356, CCW-FCV-357, CCW-FCV-363, CCW-FCV-749 and CCW-FCV-750.

CVCS-8100 and CVCS-8112.

9B26YL00.DOC 40MIS '123

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 2.3 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 2 OF 2 NO. V-RR1 Valves: Code Class: Category Description CVCS-8 100 2 A RCP Seal Water Return Isolation OC CVCS-8112 2 A RCP Seal Water Return Isolation IC CCW-FCV-356 2 A CCW to RCP's Rx Vessel Support CCW-FCV-357 2 A RCP Thermal Barrier CCW Return OC CCW-FCV-363 2 A RCP Coolers CCW Return OC CCW-FCV-749 2 A RCP Coolers CCW Return IC CCW-FCV-750 2 A RCP Thermal Barrier CCW Return IC Test Requirement: Exercise Test frequency per ISTC-3521.

Function:

These valves have an active safety function to close to provide containment isolation.

Valves: Code Class: Cateeory Description CCW-FCV-355 3 B CCW Header C Isolation Function:

This valve has an active safety function to close to isolate CCW header C in order to increase flow to the vital headers.

Basis:

These valves cannot be exercised unless reactor coolant pumps have been stopped.

Justification:

Deferral of exercising testing of these valves until either a refueling outage or extended cold shutdown outage that would allow for the reactor coolant pumps to be stopped for a sufficient period of time is preapproved perNUREG-1482, paragraph 3.1.1.4.

9B26YL00.DOC 40MIS 124

Enclosure 2 PG&E Letter DCL-05-023 REQUEST FOR RELIEF P-RR1 FOR COMPONENT COOLING WATER PUMPS THIRD TEN-YEAR INTERVAL

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 1.1 ASME/ANSI OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 2 OF 6 NO. P-RR1 System: Component Cooling Water Pumps: Pump Type Code Class: Group:

Component Cooling Water Pump 1-1 Centrifugal 3 A Component Cooling Water Pump 1-2 Centrifugal 3 A Component Cooling Water Pump 1-3 Centrifugal 3 A Component Cooling Water Pump 2-1 Centrifugal 3 A Component Cooling Water Pump 2-2 Centrifugal 3 A Component Cooling Water Pump 2-3 Centrifugal 3 A Functions:

The component cooling water (CCW) system removes heat from safety-related and nonsafety-related system components during normal operation and plant shutdown and transfers it to the ultimate heat sink via the auxiliary saltwater (ASW) system. The CCW pumps (CCWPs) are horizontally mounted centrifugal pumps.

The CCW system provides for safe shutdown and cooldown of the reactor by removing heat from safety-related and nonsafety-related system components after normal reactor shutdown, and from vital system components after an accident leading to an emergency shutdown..

Test Requirement ASME OM Code, subsection ISTB-5121(b) and ISTB-5123(b). The resistance of the system, shall be varied until flow rate equals the reference point.

Basis For Relief A variable flow measurement for the CCWP test is required because it is impractical to establish a fixed reference value(s). Relief is requested per IOCFR50.55a(f) (5) (iii). Diablo Canyon Power Plant (DCPP) had previously received relief for these pumps in the first and second 10 year plans.

9B26YL00.DOC 40MIS 12

PACIFIC GAS & ELECTRC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 1.1 ASME/ANSI OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 3 OF 6 NO. P-RRM(cont.)

The CCW system has varying heat loads, and therefore varying flow requirements. A full flow test line with a single throttle valve for the purpose of testing was not incorporated in the initial design of the system. For some plant conditions, a reference flow condition cannot be established without adversely affecting the system flow balance and Technical Specification (TS) operability requirements. Thus, these pumps must be tested in a manner that the CCW system remains properly flow balanced during and after the testing and each supplied load remains fully operable per TS to maintain the required level of plant safety during power operation. During refueling outages, CCW flow demand varies greatly due to reactor coolant system cooldown,'clearing of components for maintenance, and spent fuel pool heat exchanger cooling water demand. Past experience at DCPP has shown that CCW flow during refueling outages is usually greater than flow during power operations and it is not practical to reduce flow in order to perfonn the CCWP IST.

At a minimum, perturbation of multiple systems is required to establish a flow point due to the multiple flow paths of the CCW system. This abnormal configuration would have to be maintained for the length of time required to take vibration data and pump hydraulic data. In addition, the requirement for the Operators to manipulate valves required to adjust CCW flow to the reference point is adverse to ALARA.

Alternative Test Perform inservice tests on CCWPs using the following. A reference pump curve (flow rate vs. pump head) has been developed for each of the six CCWPs.

The following elements will be performed in developing the pump curves for testing the CCWPs. Existing data from previously performed inservice tests may be used in developing the curves. If a pump is replaced or repaired in such a way that inservice test parameters would require new reference values, then a preservice test performed per ISTB-5 100 would be used to develop the new reference pump curve and reference vibration values.

I. Pump reference curves will be developed when the pumps are known to be operating satisfactorily.

2. Instrumentation used to develop pump curves is at least as accurate (accuracy and range) as required by ASME OM Code Table ISTB-3400-1

3. Pump curves will be constructed using a minimum of five points.

4. Points used to construct the curves are beyond the flat portion (low flow rates) of the pump curve in a range, which includes the design bases flow rate.

5. Acceptance criteria for flow rate and differential pressure will be established by taking the more conservative of curves based on the limits of Table ISTB-5 100-1, or the operability criteria in TS or Safety Analysis Report.

6. Vibration levels will be measured over the range of pump conditions, and appropriate vibration acceptance criteria based on ISTB-5 100-1, will be assigned for regions of the pump curve.

7. A new reference curve will be prepared by performing a preservice test procedure in accordance with ISTB-51 1O, or the previous curve will be validated, if the pump curve is affected by replacement, repair, or routine service.

8. The comprehensive pump test will be performed at a flow that is +/-20% of design flow. Design flow for a CCW pump is 9200 gpm. The group A test will be performed at a flow rate that is at least 80% of design flow.

.9B26YLOO.DOC 40MIS 13

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UJNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 1.1 ASME/ANSI OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 4 OF 6 NO. P-RR1(cont.)

References DCPP Final Safety Analysis Report Update Docket Numbers 50-275 and 50-323; Section 9.2.2 Component Cooling Water System.

DCPP Units I and 2 Technical Specification Bases for SR 3.6.6.3.

DCPP Supplemental Safety Evaluation Number 31, "Appendix A, Safety Evaluation Pump and Valve Inservice Testing Program," paragraph 2.3.3, "Relief Request (3)."

9B26YL00.DOC 40MIS 14

Enclosure 3 PG&E Letter DCL-05-023 REQUEST FOR RELIEF P-RR2 FOR AUXILIARY SALTWATER PUMPS THIRD TEN-YEAR INTERVAL

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 1.1 ASME/ANSI OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 5 OF 6 NO. P-RR2 System: Auxiliary Saltwater Pumps: Pump Type Code Class: Group:

Auxiliary Saltwater Pump 1-1 Vertical Line Shaft 3 A Auxiliary Saltwater Pump 1-2 Vertical Line Shaft 3 A Auxiliary Saltwater Pump 2-1 Vertical Line Shaft 3 A Auxiliary Saltwater Pump 2-2 Vertical Line Shaft 3 A Functions:

The auxiliary saltwater (ASW) system supplies cooling water from the ultimate heat sink, the Pacific Ocean, to the component cooling water (CCW) heat exchangers. The CCW system, in tum, removes heat from nuclear primary plant equipment and components during normal plant operation, plant cooldowns, refueling and accident conditions, including a loss of coolant accident.

Each DCPP unit is provided with two redundant ASW trains. Each of these trains consist of a full capacity ASW pump (ASWP) and associated piping to supply the tube side of one of the CCW heat exchangers with cooling water. Each pump may also be cross-connected so as to supply the opposite train heat exchanger.

Test Requirement ASME OM Code, subsection ISTB-5221(b) and ISTB-5223(b). The resistance of the system, shall be varied until flow rate equals the reference point.

Basis For Relief Adjustment to a specific reference value for the ASWP test is not practical because the pump flow rate varies based on tide level (suction pressure) and heat exchanger differential pressure (system resistance),

which cannot be readily controlled. The CCW heat exchanger outlet throttle valves are the only valves which can be adjusted to set ASWP flow at the desired test flow. These valves are sealed in a throttled position which ensures the train can perform its required safety function under worst case conditions. A CCW heat exchanger is considered inoperable after its outlet valve is adjusted until a flow verification test is performed. The flow verification test requires that the system alignment with the most system resistance i.e.,

ASW pump #1 to CCW heat exchanger #2 (or ASW pump #f2 to CCW heat exchanger #1) be used. This realignment, test and subsequent data analysis takes several hours, during which time the CCW heat exchanger is inoperable. Diablo Canyon Technical Specifications require that the second vital CCW heat exchanger be placed in service whenever ultimate heat sink temperature is greater than 640 F. In order to meet the Technical Specification LCO, ASW pump tests performed when ultimate heat sink temperatures are above 641F must be performed with two CCW heat exchangers in service and result in test flows of up to 14,000 gpm. When the test is run with only one CCW heat exchanger in service (normal test alignment),

reference pump flow is between 11,500 and 12,500 gpm. Relief is requested per 10CFR50.55a(f) (5) (iii).

9B26YL00.DOC 40MIS 15

PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES TABLE 1.1 ASME/ANSI OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA) REV 0 (2005)

REQUESTS FOR RELIEF FROM CODE REQUIREMENTS PAGE 6 OF 6 NO. P-RR2(cont.)

Alternative Test Perform inservice tests on ASWPs using the following. A reference pump curve (flow rate vs. pump head) has been developed for each of the four ASWPs.

The following elements will be performed in developing the pump curves for testing the ASWPs:

I. Pump reference curves will be developed when the pumps are known to be operating satisfactorily.

2. Instrumentation used to develop pump curves is at least as accurate (accuracy and range) as required by ISTB-3500- 1.

3. These pump curves will be constructed using a minimum of five points.

4. Points used to construct the curves are beyond the flat portion (low flow rates) of the pump curve in a range which includes the design bases flow rate.

5. Acceptance criteria for flow rate and differential pressure will be established by taking the more conservative of curves based on the limits of Table ISTB-5200-1, or the operability criteria in TS or Safety Analysis Report.

6. Vibration levels will be measured over the range of pump conditions, and appropriate vibration acceptance criteria based on Table ISTB-5200-1, will be assigned for regions of the pump curve.

7. A new reference curve will be prepared, or the previous curve will be validated, if the pump curve is affected by replacement, repair, or routine service.

8. The comprehensive pump test will be performed at a flow rate that is +/-20% of design flow. The group A test will be performed at a flow that is at least 80% of design flow. Design flow for the ASWV pumps is 11,000 gpm.

References DCPP Final Safety Analysis Report Update Docket Numbers 50-275 and 50-323; Section 9.2.2 Component Cooling Water System.

DCPP Units I and 2 Technical Specification 3.7.8.

9B26YL00.DOC 40MIS 16-