DCL-05-023, 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 Gas and 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 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 77 Beale Street San Francisco, California 94177 Revision 0 January 7, 2005 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:
9B26YL00.DOC 40MIS I
Pacific Gas and Electric Company 77 Beale Street San Francisco, California 94177 Revision 0 January 7, 2005 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:
IOCFR50.55a(f) (4) (iv) -
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).
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.
...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.
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).
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.
The IST program for a PWR must be revised, as necessary, to meet the requirements of paragraph (f) (4).
(1) 9B26YL00.DOC 40MIS 2
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.
(2) 9826YL00.DOC 40MIS 3
Pacific Gas and Electric Company 77 Beale Street San Francisco, California 94177 Revision 0 January 7, 2005 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 requirements2. 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.
(3) 9B26YL00.DOC 40MIS 4
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.
(4) 9B26YL00.DOC 40MIS 5
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 I 1 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.
(5) 9B26YL00.DOC 40MIS 6
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 Q
A 2Y NA TEST PARAMETER NOTATION Notation N
Dp Q
V P
Frequency At least once per 92 days At least once per 366 days At least once per 731 days Not applicable Parameter Pump Speed (if variable speed)
Pump Differential Pressure Flow Rate Pump Vibration Pump Discharge Pressure 9B26YL00.DOC 40MIS 7
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)
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
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 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 Safety Injection Pump 2 Centrifugal Charging Pump I Centrifugal Charging Pump 2 Residual Heat Removal Pump I Residual Heat Removal Pump 2 Containment Spray Pump I Containment Spray Pump 2 Auxiliary Feed Pump 2 (Mtr)
Auxiliary Feed Pump 3 (Mtr)
Auxiliary Feed Pump I (Turb)
Auxiliary Saltwater Pump I Auxiliary Saltwater Pump 2 Component Cooling Water Pump I Component Cooling Water Pump 2 Component Cooling Water Pump 3 Boric Acid Transfer Pump I Boric Acid Transfer Pump 2 MU Water Transfer Pump 01 MU Water Transfer Pump 02 B
P-SIP B
P-SIP A
P-CCP A
P-CCP A
P-RHR A
P-RHR B
P-CSP B
P-CSP A
P-AFW A
P-AFW B
P-AFW A
P-ASW A
P-ASW A
P-CCW A
P-CCW A
P-CCW A
P-BAT A
P-BAT A
P-MUW A
P-MUW NA NA NA NA NA NA NA NA NA NA Q
NA NA NA NA NA NA NA NA NA Q
Q Q
Q Q.
Q Q
Q Q
Q Q
Q Q
Q Q.
Q Q
Q Q
Q NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA Q
NA Q
NA Q
Q Q
Q Q
Q Q
Q Q
NA Q
NA Q
Q Q
Q Q
NA Q
Q Q
Q Q
Q Q
Q Q
Q Q
Q Q
Q Q
Q Q
Q
- Dp 2 1455 psid
- Dp > 1455 psid
- Dp 2 2400 psid
- Dp 2 2400 psid
- Dp 2 165 psid
- Dp 2 165 psid
- Dp 2 205 psid
- Dp > 205 psid P-RR2 P-RR2 P-RRI P-RRI P-RRI
- 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 Safety Injection Pump 2 Centrifugal Charging Pump I Centrifugal Charging Pump 2 Residual Heat Removal Pump I Residual Heat Removal Pump 2 Containment Spray Pump I Containment Spray Pump 2 Auxiliary Feed Pump 2 (Mtr)
Auxiliary Feed Pump 3 (Mtr)
Auxiliary Feed Pump I (Turb)
Auxiliary Saltwater Pump I Auxiliary Saltwater Pump 2 Component Cooling Water Pump I Component Cooling Water Pump 2 Component Cooling Water Pump 3 Boric Acid Transfer Pump I Boric Acid Transfer Pump 2 MU Water Transfer Pump 01 MU Water Transfer Pump 02 B
P-SIP-A B
P-SIP-A A
P-CCP-A A
P-CCP-A A
P-RHR-A A
P-RHR-A B
P-CSP-A B
P-CSP-A A
P-AFW-A A
P-AFW-A B
P-AFW-A A
P-ASW-A A
P-ASW-A A
P-CCW-A A
P-CCW-A A
P-CCW-A A
P-BAT-A A
P-BAT-A A
P-MUW-A A
P-MUW-A NA NA NA NA NA NA NA NA NA NA 2Y NA NA NA NA NA NA NA NA NA 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y P-RR2 P-RR2 P-RRI P-RRI P-RRI 9B26YL00.DOC 40MIS 10
PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS TABLE 1.1 REV 0 (2005)
ASME OM-Code 2001 (INCLUDING 2002 AND 2003 ADDENDA)
PAGE I OF 6 RELIEF REQUEST COMPONENT RELIEF REQUEST APPROVAL STATUS P-RR_
P-RR2 Component Cooling-Water Pumps 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:
Component Cooling Water Pump Component Cooling Water Pump Component Cooling Water Pump Component Cooling Water Pump Component Cooling Water Pump Component Cooling Water Pump 1-1 1-2 1-3 2-1 2-2 2-3 Pump Type Centrifugal Centrifugal Centrifugal Centrifugal Centrifugal Centrifugal Code Class:
3 3
3 3
3 3
Group:
A A
A A
A 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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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 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)."
9B26YL00.DOC 40MIS 14
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).
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:
- 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.
9B26YL00.DOC 40MIS 16
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 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
- 9B26YL00.DOC 40MIS 17
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 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 CM EC EP EF EM EN LT Pi RT REQUIREMENT Check Valve Condition Monitoring Test Exercise of Check Valve - Full Stroke Exercise of Check Valve or Valve - Partial Stroke Exercise of Valve - Full Stroke Manual Exercise of Check Valve/Disassembly Inspection Nonintrusive Exercise of Check Valve Valve Leak Test Position Indication Test 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 Q
CS R
2Y T
RR J
S CMP FREQUENCY At least once per 92 days.
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).
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).
At least once per 731 days.
Per ASME OM Code Mandatory Appendix I for Pressure Relief Devices Tested on a rotational basis during refueling outages.
Per I0CFR50 Appendix J, Option B.
At least once per 184 days 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 FW-349 FW-350 FW-352 FW-353 FW-354 FW-355 FW-356 FW-361 FW-362 FW-363 FW-367 AUX FP-1 SUCT CK FROM CST AUX FP-2 SUCT CK FROM RWS AUX FP-2 SUCT CK FROM CST AUX FP-3 SUCT CK FROM CST AUX FP-2&3 SUCT CK FROM RWS AUX FP-2 RECIRC CK AUX FP-2 RECIRC CK AUX FP-3 RECIRC CK AUX FP-2 DISCH CK AUX FP-2 DISCH CK AUX FP-3 DISCH CK SG-2 FW CK 42-C 41-C 42-D 42-D 41-D 43-C 43-D 44-D 44-C 44-D 44-D 47-A 3
C 3
C 3
C 3
C 3
C 3
C 3
C 3
C 3
C 3
C 3
C 2
A,C 8
CK 8
CK 6
CK 6
CK 8
CK 1.5 CK 1.5 CK 1.5 CK 6
CK 4
CK 4
CK 16 CK N
N N
N N
N N
N N
N N
N C
CM CMP C CM CMP C CM CMP C CM CMP C CM CMP C
CM CMP C CM CMP C CM CMP C CM CMP C
EC CS EC CS LT 2Y 0/c o/c 0/c 0/c olc 0/c 0/c o/c o/c o/c o/c C
0 C
C 0
C V-18 V-18 V-18E V-18E V-18 V-18E V-18E V-18E V-18 V-18E V-18E V-3P3 V-26 V-3P3 V-26 CS I CS I FW-368 SG-1 FW CK 47-A 2
A,C 16 CK N
- 1
- 2-ADMIN Tested R
- l
- 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 FW-371 FW-372 FW-373 FW-374 FW-375 FW-376 FW-377 FW-378 FW-379 FW-380 AUX FP-2 TO SG-I CK AUX FP-I TO SG-2 CK AUX FP-2 TO SG-2 CK AUX FP-1 TO SG-3 CK AUX FP-3 TO SG-3 CK AUX FP-t TO SG-4 CK AUX FP-3 TO SG-4 CK SG-1 AUX FW 1 ST CK SG-2 AUX FW 1 ST CK SG-3 AUX FW 1 ST CK SG-4 AUX FW 1 ST CK 47-D 47-C 47-D 47-B 47-C 47-B 47-C 49-B 48-B 48-B 48-B 2
C 3
CK 2
C 3
CK 2
C 3
CK 2
C 3
CK 2
C 3
CK 2
C 3
CK 2
C 3
CK 2
C 3
CK 2
C 3
CK 2
C 3
CK 2
C 3
CK N
C EC N
C EC N
C EC N
C EC N
C EC N
C EC N
C EC N
C CM N
C CM N
C CM N
C CM CS CS CS CS CS CS CS CMP CMP CMP CMP o/c o/c o/c o/c o/c o/c o/c o/c o/c o/c o/c CS2 CS2 CS2 CS2 CS2 CS2 CS2 P-AFW P-AFW P-AFW P-AFW P-AFW P-AFW P-AFW V-18F V-18F V-18F 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 FW-532 SG-4 FW CK FCV-436 RWS SUP AUX FP-I FCV-437 RWS SUP AUX FP-2 & 3 FCV-438 SG-1 FW ISO FCV-439 SG-2 FW ISO FCV-440 SG-3 FW ISO FCV-441 SG-4 FW ISO LCV-106 AUX FP-I TO SG-1 REG LCV-107 AUX FP-1 TO SG-2 REG LCV-108 AUX FP-1 TO SG-3 REG LCV-109 AUX FP-1 TO SG-4 REG LCV-I 10 AUX FP-2 TO SG-I REG LCV-11I AUX FP-2 TO SG-2 REG 47-A 2
A,C 16 CK N
0 EC CS c
CS!
V-3P3 EC CS o
LT 2Y c
V-26 47-A 2
A,C 16 CK N
0 EC CS c
CS!
V-3P3 EC CS o
LT 2Y c
V-26 41-C 3
B 8
BV M
C EF Q*
o/c V-3P4 41-D 3
B 8
BV M
C EF Q*
o/c V-3P4 48-A 2
B 16 GA E
0 PI 2Y NA V-2UIC EF CS 60c CS1 V-3P2 47-A 2
B 16 GA E
0 PI 2Y NA V-2U2C EF CS 60c CSI V-3P2 47-A 2
B 16 GA E
0 P1 2Y NA V-2U3C EF CS 60c CSI V-3P2 48-A 2
B 16 GA E
0 PI 2Y NA V-2U4C EF CS 60c CS!
V-3P2 47-C 2
B 3
GL E
0 PI 2Y NA V-2UID EF Q
20o/c V-3P5 47-C 2
B 3
GL E
0 PI 2Y NA V-2U2D EF Q
20o/c V-3P5 47-B 2
B 3
GL E
0 P1 2Y NA V-2U3D EF Q
200/c V-3P5 47-B 2
B 3
GL E
0 PI 2Y NA V-2U4D EF Q
20o/c V-3P5 47-D 2
B 2
GL H
0 PI 2Y NA V-2UID EF Q
40o/c V-3P6A 47-D 2
B 2
GL H
0 PI 2Y NA V-2U2D
- 1
- 2-ADMIN Tested R
- 1
- 2-ADMIN Tested R
- Per Tech Spec
- Per Tech Spec EF Q
40o/c V-3P6A 9B26YL00.DOC 40MIS 23
PACIFIC GAS & ELECTRIC COMPANY
- INSERVICE TESTING PROGRAM PLAN - VALVES ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA)
DIABLO CANYON POWER PLANT - UNITS I & 2 TABLE 2.0 REV 0 (2005)
PAGE 8 OF 52 FEEDWATER SYSTEM VALVE VALVE NUMBER LCV-1 13 LCV-1 15 FCV-5 10 FCV-520 FCV-530 FCV-540 FCV-1510 FCV-1520 FCV-1530 FCV-1540 RV-536 RV-537 VALVE DESCRIPTION AUX FP-3 TO SG-4 REG AUX FP-3 TO SG-3 REG SG-I FW REG SG-2 FW REG SG-3 FW REG SG-4 FW REG SG-1 FW REG BYPASS SG-2 FW REG BYPASS SG-3 FW REG BYPASS SG-4 FW REG BYPASS AUX FP-I SUCT RELIEF AUX FP-2&3 SUCT RELIEF P& ID NO. 1020 03 P&ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO.
REMARKS 47-C 47-C 33A-E (38-C) 33A-D (38-D) 33A-A (38-E) 33A-C (38-D) 33A-D (37-B) 33A-C (38-D) 33A-A (38-E) 33A-B (38-E) 42-C (42-D) 41-D 2
2
-TS TS TS TS TS TS TS TS 3
3 B
B B
B B
B B
B B
B C
C 2
2 12 12 12 12 6
6 6
6 Ix1.5 IlI.5 GL GL GL GL GL GL GL GL GL GL RV RV H
H A
A A
A A
A A
A N
N 0
0 0
0 0
0 C
C C
C C
C Pl EF P1 EF EF Pl EF Pl EF Pl EF Pl EF Pl EF Pl EF Pl EF Pl RT RT 2Y Q
2Y Q
CS*
2Y CS*
2Y CS*
2Y CS*
2Y CS*
2Y CS*
2Y CS*
2Y CS*
2Y T
T NA 40o/c NA 40o/c 7c NA 7c NA 7c NA 7c NA 7c NA 7c NA 7c NA 7c NA NA NA V-2U4D V-3P6B V-2U3D V-3P6B V-3PI V-2UIC V-3PI V-2U2C V-3PI V-2U3C V-3PI V-2U4C V-3PI V-2UIC V-3PI V-2U2C V-3PI V-2U3C V-3PI V-2U4C M-77 M-77
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec I 00#
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 MS-1068 MS-2015 MS-2066 MS-3015 MS-3062 MS-4015 MS-4062 MS-5166 MS-5167 FCV-22 SG-l 10% STM DUMP ISO VALVE SG-I MS LINE CK SG-2 10% STM DUMP ISO VALVE SG-2 MS LINE CK SG-3 10% STM DUMP ISO VALVE SG-3 MS LINE CK SG-4 10% STM DUMP ISO VALVE SG-4 MS LINE CK SG-2 STM TO AUX FP-I CK SG-3 STM TO AUX FP-I CK SG-4 MSIV BYPASS 31-A 2
B 8
GA M
0 EF 31-A ISTC C
28 CK N
0 EM 30-C 2
B 8
GA M
0 EF 31-B ISTC C
28 CK N
0 EM 31-D 2
B 8
GA M
0 EF 31-D ISTC C
28 CK N
0 EM 31-E 2
B 8
GA M
0 EF 31-E ISTC C
28 CK N
0 EM 30-B 2
C 4
CK N
C EM 31-C 2
C 4
CK N
C EM 31-E 2
B 3
GL A
C Pi EF 31-C 2
B 3
GL A
C Pi EF 31-B 2
B 3
GL A
C Pi EF 31-A 2
B 3
GL A
C Pi EF 2Y RR 2Y RR 2Y RR 2Y RR RR RR 2Y Q
2Y Q
2Y Q
2Y Q
NA o/c NA o/c NA o/c NA o/c o/c o/c NA 5c NA Sc NA 5c NA Sc ROI ROI ROI ROI R02 R02 V-3RI V-18 V-3RI V-18 V-3RI V-18 V-3RI V-18 V-18 V-18 V-2U4A V-3R4 V-2U3A V-3R4 V-2U2A V-3R4 V-2UIA V-3R4 FCV-23 SG-3 MSIV BYPASS FCV-24 SG-2 MSIV BYPASS FCV-25 SG-I MSIV BYPASS 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 FCV-38 SG-3 STM TO AUX FP-I FCV41 SG-I MSIV FCV-42 SG-2 MSIV FCV-43 SG-3 MSIV FCV-44 SG-4 MSIV FCV-95 AUX FP-1 STM SUP FCV-I51 SG-I BD ISOL OC FCV-154 SG-2 BD ISOL OC 30-B 2
B 4
GA E
0 Pi EF 31-C 2
B 4
GA E
0 Pi EF 31-A 2
B 28 CK A
0 Pi EF EF 31-B 2
B 28 CK A
0 Pi EF EF 31-D 2
B 28 CK A
0 PI EF EF 31-E 2
B 28 CK A
0 PI EF EF 31-B 2
B 4
GA E
C PI EF 72-C 2
B 3
GA A
0 Pi EF 72-C 2
B 3
GA A
0 PI (72-D)
EF 2Y Q
2Y Q
2Y CS CS 2Y CS CS 2Y CS CS 2Y CS CS 2Y Q
2Y Q
2Y Q
NA 30o/c NA 30o/c NA Sc 0
NA Sc 0
NA Sc 0
NA Sc 0
NA 30o NA lOc NA lOc V-2U2E V-3R6 V-2U3E V-3R6 V-2UIA CS3 V-3R2 CS3 V-3R2 V-2U2A CS3 V-3R2 CS3 V-3R2 V-2U3A CS3 V-3R2 CS3 V-3R2 V-2U4A CS3 V-3R2 CS3 V-3R2 V-2U5B V-3R5 V-2J4 V-3S2 V-2J4 V-3S2 9B26YL00.DOC 40MIS 26
PACIFIC GAS & ELECTRIC COMPANY INSERVICE TESTING PROGRAM PLAN - VALVES ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA)
DIABLO CANYON POWER PLANT - UNITS I & 2 TABLE 2.0 REV 0 (2005)
PAGE 11 OF 52 TURBINE STEAM SYSTEM P& ID NO. 1020 04 VALVE VALVE P&ID V
NUMBER DESCRIPTION COORD C
FCV-157 FCV-160 FCV-244 FCV-246 FCV-248 FCV-250 FCV-760 FCV-761 FCV-762 FCV-763 SG-3 BD ISOL OC SG-4 BD ISOL OC SG-4 SAMPLE ISOL OC SG-3 SAMPLE ISOL OC SG-2 SAMPLE ISOL OC SG-1 SAMPLE ISOL OC SG-I BD ISOL IC SG-2 BD ISOL IC SG-3 BD ISOL IC SG-4 BD ISOL IC 72-D 72-E 72-E 72-D 72-C 72-C 71-C (70-C) 71-C (70-D) 71-D (70-D) 71-E (70-E) 30-A
- LS CAT SIZ TYP TYP POS REQ 2
B 3
GA A
0 PI EF 2
B 3
GA A
0 PI EF 2
B
.75 GL A
0 PI EF 2
B
.i5 GL A
0 Pi EF 2
B
.75 GL A
0 PI EF 2
B
.75 GL A
0 PI EF 2
B 3
GL A
0 PI EF 2
B 3
GL A
0 Pi EF 2
B 3
GL A
0 PI EF 2
B 3
GL A
0 Pi EF 2
B, P 8
GL A
C Pi EF LT TST FRQ 2Y Q
2Y Q
2Y Q
2Y Q
2Y Q
2Y Q
2Y Q
2Y Q
2Y Q
2Y Q
R R
R STR TIM NA lOc NA lOc NA lOc NA 10c NA lOc NA lOc NA Sc NA Sc NA Sc NA Sc NA 20o/40c NA REL REQ PROC NO.
V-2J4 V-3S2 V-2J4 V-3S2 V-2J4 V-3S2 V-2J4 V-3S2 V-2J4 V-3S2 V-2J4 V-3S2 V-2NI V-3R3 V-2NI V-3R3 V-2NI V-3R3 V-2N I V-3R3 V-2UIB V-3RI V-3RI REMARKS PCV-19 SG-1 10% ATM DUMP 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 PCV-21 SG-3 10% ATM DUMP PCV-22 SG-4 10% ATM DUMP 30-C 31-D 31-E 30-A 31-A 31-A 31-A 30-C 31-C 31-C 31-C 2
B, P 8
GL A
C PI R
NA EF R
20o/40c LT R
NA 2
B, P 8
GL A
C Pi R
NA EF R
20o/40c LT R
NA 2
B,P 8
GL A
C Pi R
NA EF R
20o/40c LT R
NA V-2U2B V-3RI V-3RI V-2U3B V-3R1 V-3RI V-2U4B V-3RI V-3R1 M-77 M-77 M-77 M-77 M-77 M-77 M-77 M-77 APPX I TABLE I-8220-1 APPX I TABLE I-8220-1 APPX I TABLE I-8220-1 1065#
1078#
1090#
1103#
1065#
1078#
1090#
1103#
RV-3 RV-4 RV-5 RV-6 RV-7 RV-8 RV-9 RV-10 SG-1 SAFETY SG-1 SAFETY SG-I SAFETY SG-I SAFETY SG-2 SAFETY SG-2 SAFETY SG-2 SAFETY SG-2 SAFETY 2
C 6
RV 2
C 6
RV 2
C 6
RV 2
C 6
RV 2
C 6
RV 2
C 6
RV 2
C 6
RV 2
C 6
RV N
C RT N
C RT N
C RT N
C RT N
C RT N
C RT N
C RT N
C RT T
NA T
NA T
NA T
NA T
NA T
NA T
NA T
NA 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 RV-12.
RV-13 RV-14 RV-58 RV-59 RV-60 RV-61 RV-222 RV-223 RV-224 RV-225 SG-3 SAFETY SG-3 SAFETY SG-3 SAFETY SG-3 SAFETY SG-4 SAFETY SG-4 SAFETY SG-4 SAFETY SG-4 SAFETY SG-I SAFETY SG-2 SAFETY SG-3 SAFETY SG-4 SAFETY 31-D 31-D 32-D 31-D 31-E 31-E 32-E 31-E 31-A 31-C 31-D 31-E 2
C 6
RV 2
C 6
RV 2
C 6
RV 2
C 6
RV 2
C 6
RV 2
C 6
RV 2
C 6
RV 2
C 6
RV 2
C
.6 RV 2
C 6
RV 2
C 6
RV 2
C 6
RV N
C RT N
C RT N
C RT N
C RT N
C RT N
C RT N
C RT N
C RT N
C RT N
C RT N
C RT N
C RT T
NA T
NA T
NA T
NA T
NA T
NA T
NA T
NA T
NA T
NA T
NA T
NA M-77 M-77 M-77 M-77 M-77 M-77 M-77 M-77 M-77 M-77 M-77 M-77 1065#
1078#
1090#
1103#
1065#
1078#
1090#
1103#
1115#
1115#
1115#
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 EC EC 2
A 2
GA M
LC LT J
c V-670 Tested R R
o R03 V-670 R
c R03 V-670 J
c V-670 PASSIVE Tested R AXS-26 AUX STM SUP TO CONT ISO OC 43-D 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 RCS-512 PCV-455C RV & STM LK OFF HDR TO PRT MISC EQUIP DR TANK ISOL OC PZR PORV 44-E 48-A 40-C 3
C 2
A I
B,P 4
CK N
C CM 3/4 GL M
LC LT 2
GL A
C Pi EF LT CMP J
R R
R o/c C
NA 2.9o NA V-18 V-671 V-2TI V-3J2 V-2TI RV function PASSIVE APP I TAB 1-8220-1 PCV-456 PZR PORV PCV-474 PZR PORV 40-B I
B,P 2
GL A
C PI EF LT 40-C I
B, P 2
GL A
C PI EF LT R
NA R
2.9o R
NA R
NA R
2.9o R
NA V-2TI V-3J2 V-2TI V-2TI V-3J2 V-2TI 8000A 8000B 8000C 801 OA 8010B 8010C 8028 8029 PZR PORV ISOL PZR PORV ISOL PZR PORV ISOL PZR SAFETY PZR SAFETY PZR SAFETY RV DISC HDR TO PRT ISOL IC PRI WTR TO PRT ISOL OC 41-C I
B 3
GA E
0 Pi EF 41-C I
B 3
GA E
O Pi EF 40-B I
B 3
GA E
0 Pi EF 43-D I
A,C 6
RV N
C RT 42-D I
A,C 6
RV N
C RT 42-D I
A,C 6
RV N
C RT 47-C 2
A,C 4
CK N
C LT CM 48-D 2
A 3
BA A
0 Pi LT EF 2Y Q
2Y Q
2Y Q
T T
T J
CMP 2Y J
Q NA 20c NA 20c NA 20c NA NA NA c
o/c NA c
1Oc V-2TI V-3JIA V-2TI V-3JIB V-2TI V-3JIC M-77 M-77 M-77 V-671 V-18 V-2J7 V-652A V-3S7 APP I TAB 1-8220-1 APP I TAB 1-8220-1 2485#
2485#
2485#
RV function Tested R 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 8034B PRT TO GA ISOL OC
- 8045 8046 8047 N2 TO PRT ISOL OC PRI WTR TO PRT ISOL IC N2 TO PRT ISOL IC 48-E 48-E 48-E 48-D 48-E 75-A 75-B (75-A) 75-B (75-A) 75-A 2
A 3/8 GL A
0 Pi 2Y LT i
EF Q
2 A
3/8 GL A
C Pi 2Y LT i
EF Q
2 A
3/4 DI A
0 Pi 2Y LT i
EF Q
2 A,C 3
.CK N
C LT i
EC R
EC R
2 A,C 3/4 CK N
C LT J
EC R
EC R
2 B
I GL S
LC Pi 2Y EF R
2 B
1 GL S
LC Pi 2Y EF R
2 B
1 GL S
LC Pi 2Y EF R
2 B
I GL S
NA c
lOc NA c
lOc NA c
lOc c
c 0
c 0
c NA 2o NA 2o NA 2o NA 2o V-204 V-676B V-3S8 V-2J7 V-676B V-3S8 V-2J7 V-652B V-3S8 V-652A V-652A V-652B R03 R03 R03 R03 Tested R
- 1 Tested R
- 1 Tested R Tested R Tested R Tested R 8078A REACTOR VESSEL HEAD VENT 8078B REACTOR VESSEL HEAD VENT 8078C REACTOR VESSEL HEAD VENT 8078D REACTOR VESSEL HEAD VENT V-2T2 R04 V-2T2 V-2T2 R04 V-2T2 V-2T2 R04 V-2T2 V-2T2 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 LCV-1 12B VCT OUT ISOL LCV-1 12C VCT OUT ISOL 8100 RCP SEAL WTR RETRN ISOL OC 8104 EMERG BORATE 8105 CENT CHG PP RECIRC 8106 CENT CHG PP RECIRC 8107 CHG LINE ISOL OC 8108 CHG LINE ISOL 8109 RCP SEAL WTR RETRN ISOL IC 41C-C (40B-B) 46B-C (43B-D) 47B-C (43B-D) 38C-A (39-E) 44C-C (41 B-B) 43B-E (41B-A) 43B-E (41B-A) 49D-B (47B-C) 48D-B (46B-C) 37C-A (38-D) 2 B
2 GL A
C P1 EF ISTC B
4 GA E
0 Pi EF ISTC B
4 GA E
0 PI EF 2
A 4
GA E
O Pi LT EF 2
B 2
GL E
C Pi EF ISTC B
2 GL E
0 Pi EF 2
B 2
GL E
0 Pi EF 2
B 3
GA E
0 Pi EF 2
B 3
GA E
0 Pi I
EF 2
A,C 3/4 CK N
0 LT EC 2Y Q
CS 2Y Q
R NA V-2K 1Oo V-3EI NA V-211 10c CS4 V-3K12 NA V-211 10c CS4 V-3K12 NA V-211 c
V-645 10c C55 V-3K2 NA V-2K lOo V-3E5 NA V-211 10c CS6 V-3K9 NA V-211 10c CS6 V-3K9 NA V-211 14c CS7 V-3K13 NA V-211 14c CS7 V-3K13 c
V-645 o/c RO5 V-645
- 3 - Hosgri Tested R RRI Tested R 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 8145 8146 8147 RCP SEAL WTR RETRN ISOL IC 37C-A (38-E)
PZR AUX SPRAY NORMAL CHG ALTERNATE CHG 43-B (43-D) 43-B (43-D) 42-B (42-D) 43-B (43-D) 43-C 2
A 4
GA E
O PI 2Y NA LT J
c EF CS 10c I
B 2
GL A
B 2
GL A
B 2
GL A
B 2
GL A
A 2
GL A
C PI 2Y NA LT i
c EF CS 10c V-211 V-645 CS5 V-3K2 V-2S CS8 V-3K8 V-2S CS9 V-3K5 V-2S CS9 V-3K5 V-2S CS8 V-3K8 V-2Y V-635 CS10 V-3K7A Tested R RRI 8148 PZR AUX SPRAY BYP 8149A LTDN ORF RO-27 ISOL IC 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 8149C LTDN ORF RO-27 ISOL IC 8152 LTDN LINE ISOL OC 8367A RCP-1 SEAL INJ 2ND CK IC 8367B RCP-2 SEAL INJ 2ND CK IC 8367C RCP-3 SEAL INJ 2ND CK IC 8367D RCP-4 SEAL INJ 2ND CK IC 8368A
- RCP-1 SEAL INJ IST CK IC 8368B RCP-2 SEAL INJ I ST CK IC 8368C RCP-3 SEAL INJ I ST CK IC 8368D RCP-4 SEAL INJ IST CK IC 43-C 2
A 2
GL A
0 PI LT EF 43-C 2
A 2
GL A
C Pi LT EF 44-C 2
A 2
GL A
0 PI LT EF 34-D I
C 2
CK N
0 EC (31-C)
EC 34A-D I
C 2
CK N
0 EC (33-C)
EC 34B-D I
C 2
CK N
0 EC (35-C)
EC 34C-D I
C 2
CK N
0 EC (37-C)
EC 31-D 2
A,C 2
CK N
0 LT (31-B)
EC EC 31A-D 2
A,C 2
CK N
0 LT (33-B)
EC EC 31B-D 2
A,C 2
CK N
O LT (35-B)
EC EC 31C-D 2
A,C 2
CK N
0 LT (37-B)
EC EC 2Y J
CS 2Y J
CS 2Y J
CS R
R R
R R
R R
R J
R R
J R
R J
R R
J R
R NA c
1Oc NA c
1Oc NA c
1Oc 0
c 0
c 0
c 0
c c
c 0
c c
0 c
c 0
c c
0 R06 R06 R06 R06 R06 R06 R06 R06 R03 R03 R03 R03 R03 R03 R03 R03 V-2Y V-635 CS10 V-3K7A V-2Y V-635 CS10 V-3K7A V-218 V-635 CSI I V-3K7B V-18N V-18N V-18N V-18N V-641 V-641 V-641 V-641 V-641 V-641 V-641 V-641
- 1
- 1 Tested R
- 1 Tested R
- l Tested R
- 1 Tested R
- 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 8372B 8372C 8372D 8377 8378A 8378B 8378C 8379A 8379B 8440 8445 8475 RCP-1 SEAL INJ 3RD CK IC RCP-2 SEAL INJ 3RD CK IC RCP-3 SEAL INJ 3RD CK IC RCP-4 SEAL INJ 3RD CK IC PZR AUX SPRAY CK CHG TO LOOP 3 COLD LEG CK CHG TO LOOP 4 COLD LEG CK CHG LINE CK CHG TO LOOP 3 COLD LEG CK CHG TO LOOP 4 COLD LEG CK VCT OUTLET CK EMER BORATE REV FLO CK RECIP CH7G PP-3 DISCH4 CK 33-D (3 1-C) 33A-D (33-C) 33B-D (35-C) 33C-D (37-C) 42-A (42-E) 41-B (41-E) 41-A (41-E) 43-D (43-B) 41-B (41-E) 41-A (41 -E) 48B-C (43B-C) 41C-C (411B-B) 45D-B (45B-C)
I C
2 CK N
I C
2 CK N
I C
2 CK N
I C
2 CK N
I C
2 CK N
I C
3 CK N
I
,C 3
CK N
2 C
3 CK N
I C
3 CK N
I C
3 CK N
2 C
4 CK N
2 C
2 CK N
2 C
2 CK N
O EC R
EC R
O EC R
EC R
O EC R
EC R
O EC R
EC R
C EC R
EC R
O EC R
EC R
O EC R
EC R
O EC R
EC R
O EC R
EC R
O EC R
EC R
O EC R
EC R
C EC R
EC R
O EC R
EC R
o R06
- 1 c
R06 V-18N o
R06
- 1 c
R06 V-18N o
R06
- 1 c
R06 V-18N o
R06
- 1 c
R06 V-18N o
R07 V-3K8 c
R07 V-1 8P o
R08 V-3K5 c
RO8 V-S8P o
RO8 V-3K5 c
RO8 V-18P o
RO8 V-3K5 c
RO8 V-18P o
RO8 V-3K5 c
RO8 V-S8P o
R08 V-3K5 c
R08 V-18P c
R09 M-86G o
R09 P-CCP
- I o
RO1O V-3E5 c
RO10 V-18Q o
ROI I P-PDP Tested Q c
ROI I V-25 9B26YL00.DOC 40MIS 36
PACIFIC GAS & ELECTRIC COMPANY INSERVICE TESTING PROGRAM PLAN - VALVES ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA)
DIABLO CANYON POWER PLANT - UNITS I & 2 TABLE 2.0 REV 0 (2005)
PAGE 21 OF52 CHEMICAL AND VOLUME CONTROL '
VALVE NUMBER 8478A 8478B 8479A 8479B 8483 8487A 8487B RV-8116 RV-8117 RV-8121 RV-8123 VALVE DESCRIPTION CENT CHG PP-I DISCH CK CENT CHG PP-2 DISCH CK CENT CHG PP-I RECIRC CK CENT CHG PP-2 RECIRC CK CHG FLO TO CL 3 BYPAS CK BA TRANSFER PP-2 (PP-I)
DISCH CK BA TRANSFER PP-I (PP-2)
DISCH CK PDP RV TO VCTI LETDOWN RV TO PRT RCP SEAL WTR RETURN HDR RV SEAL WTR HXI INLT RV TO VCT SYSTEM P& ID NO. 1020 08 P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO.
REMARKS 44D-C (45B-B) 44D-D (45B-A) 44D-C (44B-B) 44D-D (45B-A) 42-B (42-E) 52B-D (57B-B) 52B-E (57B-A) 44D-A (44B-D) 44-C 33B-A (37-E) 43B-D (41 B-D) 40D-B (431B-B) 2 2
2 2
2 2
2 2
2 2
NA C
C C
C C
C C
C C
C C
4 4
2 2
314 2
2 3/4x1 2
2 2
CK CK CK CK CK CK CK RV RV RV RV N
N N
N N
N N
N N
N N
C C
C C
C 0
0 C
C C
C CM CM CM CM EC EC EC EC EC EC RT RT RT RT CMP CMP CMP CMP R
R R
R R
R T
T T
T o/c 0/c o/c o/c 0
C 0
C 0
c 0
R012 R012 R013 R013 R013 RO13 V-181 V-181 V-181 V-181 V-18D V-18P P-BAT V-18R P-BAT V-18R M-77 M-77 M-77 M-77 RV function Tested Q Tested Q 2720#
600#
150#
150#
0 0
0 RV-8125 CHG PPS SUC HDR REL TO PZR 2
C 3/4 RV N
C RT T
o M-77 220#
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 8801A 8801B 8802A 8802B 8803A 8803B 8804A 8804B 8805A FC-927 ISOL OC CHG INJ TO RCS CHG INJ TO RCS SI PP-I DISCH ISOL OC Sl PP-2 DISCH ISOL OC CHG INJ TO RCS CHG INJ TO RCS CHG PP SUCT FROM RHR ST PP SUCT FROM RHR RWST TO CHG PP SUCT 42-E 43-D 43-C 54-E 54-D 45-C (45-B) 45-B 48-B 58-C 48-C 2
A 3/4 GL M
LC LT 2
B 4
GA E
C PI EF 2
B 4
GA E
C Pi EF 2
B 4
GA E
B 4
GA E
B 4
GA E
C Pi EF 2
B 4
GA E
C Pi EF 2
B 8
GA E
C PI EF 2
B 8
GA E
C PI EF 2
B
- 8 GA E
C Pi EF J
2Y Q
2Y Q
2Y Q
2Y R
2Y R
2Y CS c
NA 10o NA 10o NA 20o NA 20o NA 10o NA 10o NA 20o NA 200 NA Ho V-65 1 B V-2J6 V-3E9 V-2J6 V-3E9 V-2J6 CS12 V-3LI V-2J6 CS12 V-3LI V-2C V-3Ell V-2C V-3EI I V-2V1 R014 V-3L16 V-2VI R014 V-3L16 V-2Z CS13 V-3KI I PASSIVE 9B26YL00.DOC 40MIS 38
PACIFIC GAS & ELECTRIC COMPANY INSERVICE TESTING PROGRAM PLAN - VALVES ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA)
DIABLO CANYON POWER PLANT - UNITS I & 2 TABLE 2.0 REV 0 (2005)
PAGE 23 OF 52 SAFETY INJECTION SYSTEM VALVE NUMBER 8805B 8807A 8807B 8808A 8808B 8808C 8808D 8809A 8809B 8818A 8818B VALVE DESCRIPTION RWST TO CHARG PP SUCT Si PP1 SUC TO CCP SUC XTIE SI PPI SUC TO CCP SUC XTIE ACCUM-I DISCH ISOL ACCUM-2 DISCH ISOL ACCUM-3 DISCH ISOL ACCUM-4 DISCH ISOL RHR TO CLD LEGS-1&2 ISOL OC RHR TO CLD LEGS-3&4 ISOL OC RHR TO COLD LEG-I CK RHR TO COLD LEG-2 CK P& ID NO. 1020 09 P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO.
REMARKS 48-C 2
B 8
GA E
C Pi 2Y NA V-2Z EF CS lo CS13 V-3KI I 48-A 2
B 4
GA E
C PI 2Y NA V-2H EF Q
20o V-3L3 48-A 2
B 4
GA E
C PI 2Y NA V-2H EF Q
20o V-3L3 31-D 2
B 10 GA E
LO PI 2Y NA V-2PI EF CS 30o CS14 V-3L4 33-D 2
B 10 GA E
LO PI 2Y NA V-2PI EF CS 30o CS14 V-3L4 35-D 2
B 10 GA E
LO PI 2Y NA V-2PI EF CS 30o CS14 V-3L4 37-D 2
B 10 GA E
LO PI 2Y NA V-2PI EF CS 30o CS14 V-3L4 54-C 2
B 8
GA E
LO PI 2Y NA V-2J3 EF CS 20c CSI5 V-3L5 54-B 2
B 8
GA E
LO PI 2Y NA V-2J3 EF CS 20c CS15 V-3L5 52-C I
A,C 6
CK N
C LT R*
c V-5A2
A,C 6
CK N
C LT R*
c V-SA2
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 8818D RHRTO COLD LEG-CK 8819A Si TO COLD LEG-I CK 8819B 8819C 8819D 8820 8821A 8821B 8835 Si TO COLD LEG-2 CK SI TO COLD LEG-3 CK SI TO COLD LEG-4 CK CHG INJ 2ND OFF CK SI PP-I DISCH ISOL SI PP-2 DISCH ISOL SI COLD INJECT ISOL OC 51-B I
A,C 6
CK N
C LT CM 51-A 1
A,C 6
CK N
C LT CM 52-C I
A,C 2
CK N
C LT EC EC 51-B I
A,C 2
CK N
C LT EC EC 50-B I
A,C 2
CK N
C LT EC EC 50-B I
A,C 2
CK N
C LT EC EC 41-D I
C 3
CK N
C EC EC 55-E 2
B 4
GA E
0 PI EF 55-D 2
B 4
GA E
0 PI EF 54-C 2
B 4
GA E
CMP R*
CMP R
R R
R*
R R
R*
R R
R*
R R
R R
2Y Q
2Y Q
2Y CS C
o/c C
o/c C
C 0
C C
0 C
C 0
C C
0 C
0 NA 20c NA 20c NA 20c V-5A2 V-18B V-5A2 V-18B V-SAI RO15 V-5A1 R015 V-18D V-5AI R015 V-SAI R015 V-18D V-SAI R015 V-SAI ROI5 V-18D V-SAI R015 V-SAI R015 V-18D R016 V-SD R016 V-18D V-2J6 V-3L2A V-2J6 V-3L2B V-2J6 CS16 V-3L6
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec 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)
PAGE 25 OF 52 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA)
SAFETY INJECTION SYSTEM P& ID NO. 1020 09 VALVE NUMBER VALVE DESCRIPTION P & ID VLV VLV VLV VLV ACT NRM TST TST STR REL PROC COORD CLS CAT SIZ TYP TYP POS REQ FRQ TIM REQ NO.
REMARKS 8871 8875A 8875B 8875C 8875D 8876A 8876B 8876C 8876D 8880 8883 8900A 8900B 8900C 8900D SI TEST LINE ISOL IC SI ACCUM I NIT FILL & VENT SI ACCUM 2 NIT FILL & VENT SI ACCUM 3 NIT FILL & VENT SI ACCUM 4 NIT FILL & VENT SI ACCUM I DRAIN SI ACCUM 2 DRAIN SI ACCUM 3 DRAIN SI ACCUM 4 DRAIN N2 SUP TO ACCUM ISOL OC SI PP-I TO TST LINE ISO OC CHG INJ LOOP-I CK CHG INJ LOOP-2 CK CHG INJ LOOP-3 CK CHG INJ LOOP-4 CK 38-C 2
A 3/4 GL A
31-E 2
B I
GL A
33-E 2
B I
GL A
35-E 2
B I
GL A
37-E 2
B I
GL A
30-D 2
B I
GL A
32-D 2
B I
GL A
34-D 2
B I
GL A
37-D 2
B I
GL A
39-E 2
A I
GL A
54-E 2
A 3/4 GL A
40-E I
C 1.5 CK N
40-B I
C 1.5 CK N
40-C I
C 1.5 CK N
40-D I
C 1.5 CK N
C PI 2Y NA LT J
c EF Q
lOc C
PI 2Y NA C
PI 2Y NA C
PI 2Y NA C
PI 2Y NA C
PI 2Y NA C
PI 2Y NA C
PI 2Y NA C
PI 2Y NA 0
PI 2Y NA LT J
c EF Q
10c C
PI 2Y NA LT J
c EF Q
loc C
EC R
o EC R
c C
EC R
o EC R
c C
EC R
o EC R
c C
EC R
o EC R
c V-201 V-651B V-3S5 V-2P2 Passive V-2P2 Passive V-2P2 Passive V-2P2 Passive V-2P2 Passive V-2P2 Passive V-2P2 Passive V-2P2 Passive V-2J7 V-651A Tested R V-3S5 V-2J7 V-651B V-3S5 R016 V-18D R016 V-5D R016 V-18D R016 V-SD R016 V-18D R016 V-SD R016 V-18D 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 8905B SI TO HOT LEG-2 CK 8905C SI TO HOT LEG-3 CK 8905D SI TO HOT LEG-4 CK 8916 N2 SUP TO ACCUM CK IC 8919A SI PP-I TO RWST CK 8919B SI PP-2 TO RWST CK 8922A SI PP-I DISCH CK 8922B SI PP-2 DISCH CK 8923A SI PP-I SUCT 8923B SI PP-2 SUCT 8924 RWST TO CHG PP CK 52-E I
A,C 2
CK N
C EC R
EC R
LT R*
52-E I
A,C 2
CK N
C EC R
EC R
LT R*
51-D I
A,C 2
CK N
C EC R
EC R
LT R*
51-D I
A,C 2
CK N
C EC R
EC R
LT R*
38-E 2
A,C I
CK N
C LT J
EC R
EC R
57-E 2
C 3/4 CK N
C EC R
EC R
57-D 2
C 3/4 CK N
C EC R
EC R
56-E 2
C 4
CK N
C EC R
EC R
56-D 2
C 4
CK N
C EC R
EC R
58-E 2
B 6
GA E
0 PI 2Y EF Q
58-D 2
B 6
GA E
0 PI 2Y EF Q
48-C 2
C 8
CK N
C EC R
EC R
0 c
c 0
C C
0 c
C 0
C C
c c
0 0
c 0
c 0
c 0
c NA 30c NA 30c 0
c RO15 V-18D RO1S V-SC V-SC RO1S V-18D RO15 V-SC V-5C ROIS V-18D RO15 V-5C V-SC RO15 V-18D RO15 V-5C V-SC V-651A R03 V-651A R03 R017 P-SIP RO17 V-24 R017 P-SIP R017 V-24 R018 V-18D R018 P-SIP R018 V-18D R018 P-SIP V-2H V-3L1tOA V-2H V-3L1 OB R019 V-18D R019 M-86G
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec Tested R
- 1 Tested Q Tested Q Tested Q Tested Q 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 8948B 8948C 8948D 8949A 8949B 8949C 8949D 8956A 8956B 8956C 8956D LOOP-1 COLD INJ CK LOOP-2 COLD INJ CK LOOP-3 COLD INJ CK LOOP-4 COLD INJ CK SI TO HOT LEG-I CK Sl TO HOT LEG-2 CK SI TO HOT LEG-3 CK SI TO HOT LEG-4 CK ACCUM-1 DISCH CK ACCUM-2 DISCH CK ACCUM-3 DISCH CK ACCUM-4 DISCH CK 30-C I
A,C 10 CK N
C LT R*
A,C 10 CK N
C LT R*
A,C 10 CK N
C LT R*
A,C 10 CK N
C LT R*
A,C 6
CK N
C EC R
EC R
LT R*
50-E I
A,C 6
CK N
C EC R
EC R
LT R*
50-D I
A,C 6
CK N
C EC R
EC R
LT R*
50-D I
A,C 6
CK N
C EC R
EC R
LT R*
31-C I
A,C 10 CK N
C LT R*
A,C 10 CK N
C LT R*
A,C 10 CK N
C LT R*
A,C 10 CK N
C LT R*
o/c C
o/c C
o/c C
o/c 0
C C
0 C
C 0
C C
0 C
C C
0/c C
o/c C
o/c C
o/c V-5A2 V-18A V-5A2 V-18A V-5A2 V-18A V-5A2 V-18A R020 V-18D R020 V-SC V-5C R020 V-18D R020 V-5C V-5C R020 V-18D R020 V-5C V-SC R020 V-18D R020 V-SC V-SC V-5AI V-18A V-SAI V-18A V-SAI V-18A V-SAI V-18A
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec 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 8974A 8974B 8976 8977 SI TEST LINE ISOL OC SI RECIRC TO RWST SI RECIRC TO RWST RWST TO S1 PP ISOL
A 3/4 GL A
C PI 2Y NA V-2J7 LT J
c V-651B EF Q
10c V-3S5 58-D ISTC.
B 2
GL E
LO PI 2Y NA V-2V2 EF CS l0c CS17 V-3L15 57-D 2
B 2
GL E
LO PI 2Y NA V-2V2 EF CS loc CS17 V-3L15 59-D 2
B 8
GA E
LO PI 2Y NA V-2J6 EF CS 20c CS18 V-3L13 59-D 2
C 8
CK N
C EC R
o R021 V-15 EC R
c R021 M-86AI 8980 8981 8982A 8982B RWST TO RHR PPS ISOL OC RWST TO RHR PP CK CONT RCRC SMP TO RHRPI ISO CONT RCRC SMP TO RHRP2 ISO 59-B 2
B 12 GA E
LO PI 2Y NA V-2J3 EF CS 25c CS19 V-3L14 59-B 2
C 12 CK N
C EC R
o R022 V-4C EC R
c R022 V-4D 52-A 2
B 14 GA E
25o R023 V-3L17 53-A 2
B 14 GA E
25o R023 V-3L17 55-D 2
C 3/4 RV N
C RT T
o M-77 1750#
55-E 2
C 3/4xl RV N
C RT T
o M-77 1750#
54-D 2
C 3/4xl RV N
C RT T
o M-77 1750#
31-E 2
C I
RV N
C RT T
o M-77 700#
33-E 2
C I
RV N
C RT T
o M-77 700#
36-E 2
C I
RV N
C RT T
o M-77 700#
RV-8851 SI TO CL RELIEF TO PRT RV-8853A SI PPI DISCH TO PRT RV RV-8853B SI PP2 DISCH TO PRT RV RV-8855A ACCUM I PRES RV RV-8855B ACCUM 2 PRES RV RV-8855C ACCUM 3 PRES RV 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 RV-8856A RV-8856B RV-8858 ACCUM 4 PRES RV RHR PP1 DISCH TO PRT RV RHR PP2 DISCH TO PRT RV RWST TO ST PP SUCT RV 38-E 54-B 54-B 58-D 2
C 1
2 C
2X3 2
C 2X3 2
C 3/4 RV RV RV RV N
C RT N
C RT N
C RT N
C RT T
o T
o T
o T
o M-77 M-77 M-77 M-77 700#
606#
606#
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 FCV-641B RHR PP-2 RECIRC HCV-637 RHR HX-2 OUTLET HCV-638 RHR HX-I OUTLET 8700A 8700B 8701 8702 8703 RHR PP-I SUCT OC RHR PP-2 SUCT OC RCS LOOP-4 TO RHR IC RCS LOOP-4 TO RHR RHR TO HOT LEGS-I, 2 IC 34-E 2
B 2
GL E
C PI 2Y EF Q
34-B 2
B 2
GL E
C PI 2Y EF Q
31-B 2
B 8
BA A
0 EF Q
(31-C)
PI 2Y 31-D 2
B 8
BA A
0 EF Q
Pl 2Y 37-D 2
B 14 GA E
0 PI 2Y (36-D)
EF Q
37-B 2
B 14 GA E
0 PI 2Y (36-B)
EF Q
38-D I
A 14 GA E
EF CS 39-D I
A 14 GA E
LC P1 2Y (38-D)
LT R*
EF CS 38-A 2
A 12 GA E
NA I Oo/c NA I Oo/c 30O NA 30o NA NA 120c NA 120c NA C
160o/c NA C
160o/c NA 85o C
V-2D V-3MIA V-2D V-3MIB V-3M2B V-2J3 V-3M2A V-2J3 V-2D2 V-3M4A V-2D2 V-3M4B V-2D3 V-7C CS20 V-3M5 V-2D3 V-7C CS20 V-3M5 V-2M3 CS21 V-3M6 V-5C
- Per Tech Spec
- Per Tech Spec
- 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 8716B RHR TRAIN XTIE OC 30-C 8730A RHR PP-I DISCH CK 35-D 8730B RHR PP-2 DISCH CK 35-B (35-C) 8740A RHR TO HOT LEG-I CK 39-B 8740B RHR TO HOT LEG-2 CK 39-A 8742A RH-R HT EX-l DISCH CK 32-D 8742B RHR HT EX-2 DISCH CK 32-B (32-C)
RV-8707 RHR PPS SUCT FROM HL4 RV 38-D 2
2 2
2 I
1 2
2 2
B B
C C
A/C A/C C
C C
8 8
8 8
8 8
8 8
3x4 GA GA CK CK CK CK CK CK RV E
E N
N N
N N
N N
0 0
C C
C C
C C
C PI EF Pl EF CM CM CM LT CM LT EC EC EC EC RT 2Y CS 2Y CS CMP CMP CMP R*
CMP R*
NA 20o/c NA 20o/c o/c o/c o/c C
o/c C
a C
0 c
0 CS22 CS22 CS23 CS23 CS23 CS23 V-2J3 V-3M7 V-2J3 V-3M7 P-RHR-A P-RHR-A V-18C V-SC V-18C V-5C V-4B P-RHR V-4B P-RHR M-77 M-77
- Per Tech Spec
- Per Tech Spec Tested Q Tested Q 455#
606#
RV-8708 RHR TO HLI&2 TO PRT RV (37-D) 38-B (37-B) 2 C
3/4xl RV N
C RT T
o 9B26YL00.DOC 40MIS 47
PACIFIC GAS & ELECTRIC COMPANY INSERVICE TESTING PROGRAM PLAN - VALVES ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA)
NUCLEAR STEAM SUPPLY SAMPLING SYSTEM VALVE VALVE P & ID VLV VLV VLV NUMBER DESCRIPTION COORD CLS CAT SIZ 9354A PZR STM SAMPLE ISOL IC 21-A 2
A 3/8 9354B PZR STM SAMPLE ISOL OC 22-A 2
A 3/8 9355A PZR LIQUID SAMPLE ISOL IC 21-B 2
A 3/8 9355B PZR LIQUID SAMPLE ISOL OC 22-B 2
A 3/8 9356A HOT LEG SAMPLE ISOL IC 21-B 2
A 3/8 DIABLO CANYON POWER PLANT - UNITS I & 2 TABLE 2.0 REV 0 (2005)
PAGE 32 OF 52 P& IDNO. 1020 11 VLV ACT NRM T!
TYP TYP POS R GL A
0 PI L'
El GL A
0 P1 L'
E]
GL A
0 PI L
E]
GL A
0 P
L E
GL A
O P1.
L' E]
F I
.F T
FT F
T F
TST FRQ 2Y J
Q 2Y J
Q 2Y J
Q 2Y i
Q 2Y J
Q STR REL TIM REQ NA c
lOc NA c
1Oc NA c
lOc NA c
lOc NA c
lOc PROC NO.
V-203 V-676A V-3SI V-2JI V-676A V-3SI V-203 V-659A V-3SI V-2JI V-659A V-3SI V-203 V-659B V-3SI REMARKS 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 9357A ACCUM SAMPLE ISOL IC 9357B ACCUM SAMPLE ISOL OC 22-B 2
A 3/8 GL A
0 Pi 2Y NA LT J
c EF Q
21-C 2
A 3/8 GL A
0 Pi 2Y LT J
EF Q C 2
A 3/8 GL A
0 Pi 2Y LT J
EF Q
1Oc NA c
lOc NA c
lOc V-2JI V-659B V-3SI V-203 V-659C V-3SI V-2JI V-659C 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-32 8992 8994A 8994B 8998A 8998B 9001A 9001B CS PP-I TO MEDT ISOL OC CS PP-2 TO MEDT ISOL OC CS ADD TK STOP NaOH CS EDUCTOR ISOL NaOH CS EDUCTOR ISOL CS ADD TK OUT CK CS ADD TK OUT CK CS PP-I ISOL CS PP-2 ISOL 33-D 2
A
.75 GL M
LC LT J
33-B 2
A
.75 GL M
LC LT J
37-B 2
B 3
GA E
B 3
GA E
B 3
GA E
A,C 3
CK N
C EC R
LT 2Y EC R
35-B 2
A,C 3
CK N
C EC R
LT 2Y EC R
34-D 2
A 8
GA E
C PI 2Y LT J
EF Q
34-A 2
A 8
GA E
C PI 2Y LT J
EF Q
c c
NA NA oo NA I oo 0
,c 0
c c
NA c
oo NA c
I o V-631 V-630 V-2G V-2G CS24 V-312 V-2G CS24 V-312 R024 V-3II V-21 R024 V-21 R024 V-311 V-21 R024 V-21 V-2B V-631 V-313A V-2B V-630 V-313B PASSIVE Tested R PASSIVE Tested R PASSIVE Tested R Tested R 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 9002B 9003A 9003B 901 IA 901 1B RV-930 RV-931 RV-8987 RV-9007A RV-9007B CS PP-I DISCH CK CS PP-2 DISCH CK RHR HX-I TO CS-A HDR RHR HX-2 TO CS-B HDR CS HDR-A ISOL CK IC CS HDR-B ISOL CK IC CS ADD TKI VAC BREAK CS ADD TK2 VAC BREAK CS ADD TKI TO AUX BLDG SMP CS HDR A OC RV CS HDR B OC RV 33-D 2
C 8
CK N
C CM 33-A 2
C 8
CK.
N C
CM 33-D 2
B 8
GA E
C Pi EF 33-B 2
B 8
GA E
C PI EF 32-D 2
A,C 8
CK N
C LT CM 32-A 2
A,C 8
CK N
C LT CM 37-D 2
C 1.5 RV N
C RT 37-C 2
C 1.5 RV N
C RT 38-C 2
C 3/4xl RV N
C RT 32-D 2
C 3/4 RV N
C RT 32-B 2
C 3/4 RV N
2Y R
J CMP J
CMP T
T T
T T
o/c o/c NA 1So NA 150 c
o/c c
o/c 0
0 0
0 0
CSP-A CSP-A V-2B2 R014 V-3I4 V-2B2 R014 V-3I4 V-631 M-86H V-630 M-86H M-77 M-77 M-77 M-77 M-77 Tested R Tested R
-l.Sf vac 1,5# vac 10#
260#
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 BETWEEN HDRS B&C CCW-5 SUCT X-TIE VLV BETWEEN HDRS A&C CCW-16 CCW PP 2 DISCH TO HEADER B CCW-17 CCW PP 3 DISCH TO HEADER B CCW-18 CCW PP 1 DISCH TO HEADER A CCW-19 CCW PP 2 DISCH TO HEADER A CCW-23 CCW HEADER A TO C ISOLATION VALVE CCW-24 CCW HEADER B TO C ISOLATION VALVE 50-C 3
B 20 BV M
LO EF 2Y NA 52-C 3
B 20 BV M
LO EF 2Y NA 53-D 3
B 20 BV M
LO EF 2Y NA V-3H15 54-D (55-D) 51-E 3
B 20 BV M
LO EF 2Y NA 3
B 20 BV M
LO EF 2Y NA V-3H15 P-CCW Tested Q P-CCW Tested Q P-CCW Tested Q P-CCW Tested Q P-CCW Tested Q P-CCW Tested Q 53-E 3
B 20 BV M
LO EF 2Y NA 58-E 3
B 24 BV M
LO EF 2Y NA 58-D 3
B 24 BV M
LO EF 2Y NA 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 NUMBER VALVE DESCRIPTION P&ID VLV COOR CLS VLV VLV VLV CAT SIZ TYP ACT NRM TST TST TYP POS REQ FRQ STR REL PROC TIM REQ NO.
REMARKS D
CCW-581 CCW FCV-749 BYPASS CK IC CCW-585 CCW TO RCP & RX VSL SUPPORT CK IC 71-B 2
A,C 3/4 CK N
C LT EC EC 72-E 2
A,C 10 CK N
0 LT EC EC 51-E 3
C 20 CK N
0 CM 53-E 3
C 20 CK N
0 CM 54-E 3
C 20 CK N
0 CM R
R R
J R
0 C
C C
0 0/c 0/c o/c V-620 ROS V-620 RO5 V-620 V-619 R03 V-619 R03 V-CCW-CK V-CCW-CK V-CCW-CK CCW-601 CCW-602 CCW-603 CCW-607 CCWV-608 CCW-609 CCW PP-I 1HDR-A CK CCW PP-2 HDR-A CK CCW PP-3 HDR-A CK CCW PP-I HDR-B CK CCW PP-2 HDR-B CK CCW PP-3 HDR-B CK CCW-670 CCW FCV-750 BYPASS CK IC CCW-695 CCW TO EXCS LTDN HX CK OC FCV-355 CCW HDR-C ISOL FCV-356 CCW TO RCP & RX VSL SUPPORT ISOL OC (55-E) 51-D 53-D 54-D (55-D) 73-B 98-D 58-D (59-D) 72-E -
3 C
20 CK 3
C 20 CK 3
C 20 CK N
0 CM CMP o/c o/c o/c V-CCW-CK V-CCW-CK V-CCW-CK 2
A,C 3/4 CK N
C LT EC EC 2
A,C 4
CK N
0 LT EC EC 3
B 20 BV E
0 PI EF 2
A 10 BV E
0 PI LT EF 2
A 6
GL E
0 Pi LT EF J
R R
J R
R 2Y CS 2Y J
CS 2Y J
CS C
0 C
c c
0 NA 20c NA c
25c NA C
30c Tested R RV function Tested R
- l PEP PEP PEP PEP PEP PEP Tested R RV function Tested R
- 1 RRI Tested R RRI Tested R RRI ROS RO5 R03 R03 V-621 V-621 V-621 V-623 V-623 V-2F CS25 V-3H3 V-2J2 V-619 CS25 V-31-14 V-2J2 V-621 CS25 V-3H5 FCV-357 RCP THM BAR CCW RTN ISO OC 73-B 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 FCV-363 RCP'S CLR CCW RTN ISOL OC FCV-364 RHR HX-2 CCW RETURN FCV-365 RHR HX-1 CCW RETURN FCV-430 CCW HX-1 OUT ISOL FCV-431 CCW HX-2 OUT ISOL FCV-749 RCP'S CLR CCW RTN ISOL IC FCV-750 RCP THM BAR CCW RTN ISO IC 98-B
-2 A
4 BV A
C Pi LT EF 72-B 2
A 6
BV E
0 PI LT EF 60-C 3
B 12 BV A
C Pi EF 104-C 3
B 12 BV A
C Pi EF 57-E 3
B 30 BV E
0 PI (58-E)
EF 57-D 3
B 30 BV E
0 PI (58-D)
EF 72-B 2
A 6
BV E
0 PI LT EF 73-B 2
A 6
GL E
0 PI LT EF 55-B 3
B 3
GL A
C EF 55-B 3
B 3
GL A
C EF 56-C 3
B 3
BA A
0 PI EF 2Y J
Q 2Y J
CS 2Y Q
2Y Q
2Y Q
2Y Q
2Y J
CS 2Y J
CS Q
Q 2Y Q
NA c
lOc NA c
25c NA 10o NA 10o NA 30O NA 30O NA c
20c NA c
30c 20o 20o NA 1Oc V-2J2 V-623 V-3S6 V-2J2 V-620 CS25 V-3H6 V-2H V-3H7 V-2H V-3H7 V-2F V-3H8 V-2F V-3H8 V-202 V-620 CS25 V-3H10 V-202 V-621 CS25 V-3H9 V-3111 I V-3H11 V-2F V-3H12 Tested R Tested R RRI Tested R RRI Tested R RRI LCV-69 LCV-70 RCV-16 MU WTR TO CCW HDR-A MU WTR TO CCW HDR-B CCW SURGE TK VENT 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 RV-42 RV-43 RV-44 RV-45 RV-46 RV-47 RV-51 RV-52 RCP3 THRML BARRIER CCW RTN RCP4 THRML BARRIER CCW RTN RCP2 THRML BARRIER CCW RTN RCP1 THRML BARRIER CCW RTN CCW SURGE TANK RV FCV-365 BYPASS RV CCW RTN FROM RHR HX2 RV RCP'S LO CLG RTN TO CCW RV CCW RTN XCES LTDN HX RV 72-C 73-C 70-C 74-C 57-C 103-C 61-C 72-C 98-C 3
C 3/4xl 3
C 3/4xl 3
C 3/4xl 3
C 3/4xl 3
C 3x4 3
C 3/4xl 3
C 3/4xl 3
C 3
2 C
3 RV RV RV RV RV RV RV RV RV N
C RT N
C RT N
C RT N
C RT N
C RT N
C RT N
C RT N
C RT N
C RT T
0 T
0 T
0
.T 0
T 0
T 0
T 0
T 0
T 0
M-77 M-77 M-77 M-77 M-77 M-77 M-77 M-77 M-77 2485#
2485#
2485#
2485#
30#
70#
70#
150#
150#
9B26YL00.DOC 40MIS 55
PACIFIC GAS & ELECTRIC COMPANY INSERVICE TESTING PROGRAM PLAN - VALVES ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA)
DIABLO CANYON POWER PLANT - UNITS I & 2 TABLE 2.0 REV 0 (2005)
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 MU-965 CST TO MU H20 XFR PPS CK MU-966 MU WATER PP RECIRC CK MU-968 MU H20 XFR PP-01 DISCH CK MU-969 MU WATER PP RECIRC CK MU-970 MU H20 XFR PP-02 DISCH CK MU-971 MU H20 TO MISC SOURCES CK MU-1555 CST H20 MIXING PP DISCH CK MU-1557 RAW WATER SUPPLY HDR ISOL 71-C (78-C) 70-D (78-D) 73-D 74-D 76-D 75-D 72-E (78-E) 71-C (78-D) 57A-D 3
C 2
CK N
C 4
CK N
C 4
CK 3
C 4
CK 3
C 4
CK 3
C 4
CK 3
C 4
CK 3
C 3
CK 3
B 8
BV V-18 N
0 N
C N
0 N
C N
C N
0 M
LC CM CM CM CM EC EC EC EC EF CMP CMP CMP CMP R
R Q
Q 2Y o/c o/c o/c o/c o
R025 c
R025 c
0 NA V-18 V-18 P-MUW-A1 V-18 P-MUW-A2 V-3U2 V-3U3 V-3UI V-3UI P-MUW-A 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 32B-D 3
C 3
CK N
C EC 2Y o/c V-18M VAC Breaker V-18M VAC Breaker SW-170 ASW PP-I DISCH VAC RELIEF SW-200 ASW PP-I DISCH CK SW-201 ASW PP-2 DISCH CK SW-301 ASW PP-2 DISCH VAC RELIEF SW-303 ASW PP-2 DISCH VAC RELIEF FCV-495 ASW PP-2 CROSS TIE FCV-496 ASW PP-I CROSS TIE FCV-601 ASW UNIT CROSS TIE FCV-602 CCW HX-I SW INLET 32B-A 32B-C 31B-D 3
C 24 CK N
0 EC 3
C 24 CK N
0 EC 3
C 3
CK N
C EC QQ 2Y o/c o/c o/c P-ASW P-ASW V-18M VAC Breaker 31B-D 3
C 3
CK N
C EC 2Y o/c V-18M VAC Breaker 33B-B 3
B 24 BV E,M 0
B 24 BV E,M 0
B 24 BV E
B 24 BV A
0 PI EF 2Y Q
2Y 2Y Q
2Y 2Y Q
2Y 2Y Q
Q 2Y Q
Q NA 30 o/c NA NA 30 o/c NA NA 30o NA NA 60o V-2AI V-3F1 V-2AI V-2AI V-3F2 V-2AI V-2A2 V-3F3 V-2A2 V-2F V-3F4 V-3F4 V-2F V-3F5 V-3F5 Manual Stroke Manual Stroke Manual Stroke UNIT I UNIT 2)
UNIT I UNIT 2)
FCV-603 CCW HX-2 SW INLET (EF 35B-C 3
B 24 BV A
0 PI EF (EF 120o NA 60o 900 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.
CONT FIREWATER ISOL IC 73-B (73-D) 72-B FCV-633 CONT FIREWATER ISOL OC FP-306 FIREWATER SUPPLY TO AUX FEED PPS FP-307 FIREWATER SUPPLY TO AUX FEED PPS 2
A,C 4
CK N
C LT J
c EC R
c EC R
o 2
A 3
GL A
0 PI 2Y NA LT i
NA EF Q
lOc 3
B 8
BV M
C EF Q*
NA V-679 R026 V-679 R026 M-63H V-2J7 V-679 V-3S4 V-3P4 I(72-E) 37-C
- Per Tech Specs 37-C 3
B 8
BV M
C EF Q*
NA V-3P4
- Per Tech Specs 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 FCV-253 RCDT PP DISCH ISOL IC FCV-254 RCDT PP DISCH ISOL OC FCV-255 RCDT VENT ISOL IC FCV-256 RCDT VENT ISOL OC FCV-257 RCDT GAS ANAL ISOL OC 38-C 2
A,C 3/4 CK N
C LT J
EC R
EC R
38-A 2
A 2.5 BA A
0 PI 2Y LT i
EF Q
39-A 2
A 2.5 BA A
0 PI 2Y LT J
EF Q
38-B 2
A 3/4 BA A
0 PI 2Y LT J
EF Q
39-B 2
A 3/4 BA A
0 PI 2Y LT i
EF Q
39-B 2
A 1/2 BA A
C Pi 2Y LT i
EF Q
c 0
NA c
lOc NA c
lOc NA c
lOc NA c
1Oc NA c
lOc V-652D V-652D Tested R R03 R03 V-205 V-650 V-3S3 V-2J5 V-650 V-3S3 V-205 V-651C V-3S3 V-2J5 V-651C V-3S3 V-2J5 V-651D V-3S3 9B26YL00.DOC 40MIS 59
PACIFIC GAS & ELECTRIC COMPANY INSERVICE TESTING PROGRAM PLAN - VALVES ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA)
LIQUID RADWASTE SYSTEM VALVE VALVE P & ID VLV VLV V NUMBER DESCRIPTION COORD CLS CAT S
FCV-258 RCDT GAS ANAL ISOL IC 38-B 2
A I
FCV-260 N2 TO RCDT ISOL OC 38-C 2
A FCV-500 CONT SUMP DISCH ISOL IC 38-D 2
A FCV-501 CONT SUMP DISCH ISOL OC 39-D 2
A FCV-696 RX CAV SUMP SMPL SUP ISO IC 38-B 2
A FCV-697 RX CAV SUMP SMPL SUP ISO OC 39-B 2
A DIABLO CANYON POWER PLANT - UNITS I & 2 TABLE 2.0 REV 0 (2005)
PAGE 44 OF 52
'LV
- IZ 1/2 2/4 2
2 3/8 3/8 P& ID NO. 1020 19 VLV ACT NRM TYP TYP POS BA A
0 BA A
0 BA A
0 BA A
0 GL S
C GL S
C TST REQ PI LT EF PI LT EF PI LT EF PI LT EF PI LT EF PI LT EF TST FRQ 2Y J
Q 2Y i
Q 2Y i
Q 2Y i
Q 2Y i
CS 2Y J
CS STR REL TIM REQ NA c
lOc NA c
lOc NA c
1Oc NA c
lOc NA c
10o CS26 NA c
1Oo CS26 PROC NO.
V-205 V-651 D V-3S3 V-2J5 V-652D V-3S3 V-205 V-649 V-3S3 V-2J5 V-649 V-3S3 V-682A V-682A V-3T5 V-682A V-682A V-3T5 REMARKS Tested R Tested R Tested R 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 8787 8795 8796 REFUEL WTR PURIF ISOL OC REFUEL WTR PURIF ISOL OC REFUEL WTR PURIF ISOL IC REFUEL WTR PURIF ISOL IC 39-C 39-D 38-C 38-D 2
A 4
DI M
LC LT 2
A 4
DI M
LC LT 2
A 4
DI M
LC LT 2
A 4
DI M
LC LT J
C J
c J
c J
C V-646 V-646 V-646 V-646 PASSIVE PASSIVE PASSIVE PASSIVE 9B26YL00.DOC 40MIS 61
PACIFIC GAS & ELECTRIC COMPANY INSERVICE TESTING PROGRAM PLAN - VALVES ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA)
DIABLO CANYON POWER PLANT - UNITS I & 2 TABLE 2.0 REV 0 (2005)
PAGE 46 OF 52 VENTILATION AND AIR CONDITIONING SYSTEM P& ID NO. 1020 23 VALVE VALVE NUMBER DESCRIPTION VAC-1 VAC-2 VAC-21 CHP SUP FAN-I ISOL OC CHP SUP FAN-2 ISOL OC CONT AIR SMPL RTN ISOL IC VAC-116 CONT AIR SMPL POST LOCA.
RTN ISOL IC VAC-200 CHP SUP ISOL IC CK VAC-201 CHP SUP ISOL IC CK VAC-252 CONT H2 SAMPLE RTN CK IC VAC-253 CONT H2 SAMPLE RTN CK IC FCV-235 CONT H2 SAMPLE SUP ISOL IC P & ID VLV VLV VLV VLV ACT NRM TST COORD CLS CAT SIZ TYP TYP POS REQ 34-A 2
A 4
GA M
LC LT 34-A 2
A 4
GA M
LC LT 44-B 2
A,C 2
CK N
0 LT CM 44-C 2
A,C 3/8 CK N
C LT EC EC 35-A 2
A,C 4
CK N
C LT CM 35-A 2
A,C 4
CK N
C LT CM 44-D 2
A,C 3/8 CK N
C LT EC 44-E 2
A,C 3/8 CK N
C LT (44-D)
EC 44-C 2
A 3/8 GL S
LC PI LT EF TST STR REL PROC J
J J
CMP R
R R
J CMP J
CMP J
R J
R 2Y J
CS c
c c
o/c c
C 0
C o/c c
0o/C C
0/C C
o/C NA C
I oo FRQ TIM REQ NO.
V-683 V-683 V-668 V-18 V-682B R03 V-682B R03 V-683 V-18 V-683 V-18 V-678 R027 V-678 V-678 R027 V-678 V-678 V-678 CS26 V-3T3 REMARKS PASSIVE Tested R PASSIVE Tested R Tested R
- 1 Tested R Tested R Tested R Tested R Tested R 9B26YL00.DOC 40MIS 62
PACIFIC GAS & ELECTRIC COMPANY INSERVICE TESTING PROGRAM PLAN - VALVES ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA)
VENTILATION AND AIR CONDITIONING SYSTEM VALVE VALVE P & ID VLV VLV VI NUMBER DESCRIPTION COORD CLS CAT SI FCV-236 CONT H2 SAMPLE SUP ISOL OC 46-C 2
A 3/
FCV-237 CONT H2 SAMPLE RTN ISOL OC 46-D 2
A 3/
FCV-238 CONT H2 SAMPLE SUP ISOL IC 44-D 2
A 3/
FCV-239 CONT H2 SAMPLE SUP ISOL OC 46-D 2
A 3/
FCV-240 CONT H2 SAMPLE RTN ISOL OC 46-E 2
A 3/
(46-D)
DIABLO CANYON POWER PLANT - UNITS I & 2 TABLE 2.0 REV 0 (2005)
PAGE 47 OF 52 IV
,Z
'8
'8
/8
'8
'8 P& ID NO. 1020 23 VLV ACT NRM TYP TYP POS GL S
LC GL S
LC GL S
LC GL S
LC GL S
LC TST REQ PI LT EF Pl LT EF PI LT EF Pl LT EF Pl LT EF TST FRQ 2Y J
CS 2Y J
CS 2Y J
CS 2Y J
CS 2Y i
CS STR TIM NA c
10o NA c
10o NA c
10o NA c
10o NA c
10o REL PROC REQ NO.
V-678 V-678 CS26 V-3T3 V-678 V-678 CS26 V-3T3 V-678 V-678 CS26 V-3T3 V-678 V-678 CS26 V-3T3 V-678 V-678 CS26 V-3T3 REMARKS Tested R Tested R Tested R Tested R Tested R 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 FCV-659 CHP EXH SYS #I DISCH ISO IC FCV-660 CONT PURGE SUP ISOL IC FCV-661 CONT PURGE SUP ISOL OC FCV-662 CONT EXCESS PRESNVAC RLF ISOL IC 35-B 2
A 4
GA E
EF CS 35-B 2
A 4
GA E
EF CS 35-C 2
A 48 BV A
C PI 2Y LT 2Y*
EF CS 34-C 2
A 48 BV A
C PI 2Y LT 2Y*
EF CS 35-B 2
A 12 BV A
C PI 2Y LT 2Y*
EF Q
NA C
150 NA c
150 NA c
2c NA C
2c NA C
Sc V-2X V-681 CS26 V-3T3 V-2X V-657 CS26 V-3T3 V-2Q V-661 CS27 V-3T7 V-2EI V-661 CS27 V-3T7 V-2Q V-663 V-3T6 Tested R Tested R
- Per Tech Spec
- Per Tech Spec
- Per Tech Spec 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 FCV-664 CONT VAC RLF OC FCV-668 CHP EXH SYS #2 DISCH ISO OC FCV-669 CHP EXH SYS # IDISCH ISO OC FCV-678 CONT AIR SAMPLE SUP ISOL IC 31-B 2
A 12 BV A
C PI 2Y LT 2Y*
EF Q
32-C 2
A 12 BV A
C PI 2Y LT 2Y*
EF Q
34-B 2
A 4
GA E
EF CS 34-B 2
A 4
GA E
EF CS 44-A 2
A I
BA A
0 PI 2Y LT J
EF Q
NA C
Sc NA C
Sc NA C
15o NA C
150 NA C
lOc V-2E3 V-663 V-3T6 V-2E3 V-663 V-3T6 V-2X V-681 CS26 V-3T3 V-2X V-657 CS26 V-3T3 V-203 V-668 V-3TI
- Per Tech Spec
- Per Tech Spec Tested R Tested R Tested R 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 FCV-681 AIR SAMPLE RETURN ISOL OC FCV-698 AIR SAMPLE POST LOCA SUP ISOL OC FCV-699 AIR SAMPLE POST LOCA SUP ISOL OC FCV-700 AIR SAMPLE POST LOCA SUP ISOL OC RCV-I I PURGE EXHAUST ISOL IC RCV-12 PURGE EXHAUST ISOL OC 46-A 2
A I
BA A
0 PI LT EF 46-B 2
A I
BA A
0 PI LT EF 44-B 2
A 3/8 GL S
C PI LT EF 46-B 2
A 3/8 GL S
C PI LT EF 46-C 2
A 3/8 GL S
C PI LT EF 35-C 2
A 48 BV A
C PI LT EF 34-C 2
A 48 BV A
C PI LT EF 2Y J
Q 2Y i
Q 2Y R
Q 2Y i
Q 2Y i
Q 2Y 2Y*
CS 2Y 2Y*
CS NA C
lOc NA C
1Oc NA C
10Oo/c NA Cloc 1 0o/c NA C
I Oo/c NA 2c NA C
2c V-2JI V-668 V-3TI V-2JI V-668 V-3TI V-682B V-682B V-3T4 V-682B V-682B V-3T4 V-682B V-682B V-3T4 V-2Q V-662 CS27 V-3T7 V-2E2 V-662 CS27 V-3T7 Tested R Tested R Tested R Tested R Tested R Tested R Tested R Tested R
- Per Tech Spec
- Per Tech Spec 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 AIR-S-200 CONT SERV AIR SUP ISOL OC AIR-1-585 CONT NORM INST AIR SUP ISOL BYPASS OC AIR-I-587 CONT NRM INST AIR SUP CK IC FCV-584 CNT NRM INST AIR SUP ISO OC (45-B) 42-D (43-B) 42-C (43-C) 42-D (44-B) 42-C (44-C)
EC EP 2
A 3
BA M
LC LT 2
A 1.5 DI M
LC LT 2
A,C 2
CK N
0 LT EC EP 2
A 2
BA A
0 Pi LT EF R
R 3
c 0
c J
c R03 V-656 R03 V-656 V-656 PASSIVE Tested R V-654 PASSIVE Tested R V-654 Tested R R
R R
2Y Q
c c
0 NA c
lOc R03 V-654 R03 V-654 V-2J7 V-654 V-3S4 Tested R 9B26YL00.DOC 40MIS 67
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 52 OF 52 REMARKS
- 1 The open safety function of check valves listed below are verified during normal operations at the frequencies noted per ISTC-3550.
Valve #
FW-367 FW-368 FW-531 FW-532 RCS-8046 RCS-8047 CVCS-8440 CVCS-8367A-D CVCS-8368A-D CVCS-8372A-D SI-8916 CCW-585 CCW-695 LWS-60 VAC-1 16 Valve Description Main Feedwater to SG#2 Check Main Feedwater to SG# I Check Main Feedwater to SG#3 Check Main Feedwater to SG#4 Check Primary Water to PRT Nitrogen to PRT VCT Outlet Check Valve RCP Seal Injection Inlet Check RCP Seal Injection Inlet Check RCP Seal Injection Inlet Check Nitrogen Supply to the Accumulators CCW to Reactor Coolant Pumps and Rx Vessel Support Cooler (IC)
Nitrogen to RCDT Check Valve (IC)
Containment Air Post Accident Sample Return Check Valve (IC)
Procedure #
STP R-2B2 STP R-2B2 STP R-2B2 STP R-2B2 OP A-4B:I OP A-4B:I STP P-CCP STP M-54 STP M-54 STP M-54 OP B-3B:I OP F-2:I OP A-6:1 OPL-1 &
OP B-IA:IV OP G-l:VI STP G-14 Frequency Daily Daily Daily Daily Refueling Outage Refueling Outage Quarterly Monthly Monthly Monthly Refueling Outage Refueling Outage Refueling Outage Refueling Outage Refueling Outage
- 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.
- 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).
9B26YL00.DOC 40MIS 69
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 2 OF 27 NO. V-CS2 Valves:
FW-369 FW-370 FW-371 FW-372 FW-373 FW-374 FW-375 FW-376 Catef!orT:
C Aux Feedwater Pump #I to Steam Generator #1 Check Valve Aux Feedwater Pump #2 to Steam Generator #I Check Valve Aux Feedwater Pump #I to Steam Generator #2 Check Valve Aux Feedwater Pump #2 to Steam Generator #2 Check Valve Aux Feedwater Pump #I to Steam Generator #3 Check Valve Aux Feedwater Pump #3 to Steam Generator #3 Check Valve Aux Feedwater Pump #I to Steam Generator #4 Check Valve Aux Feedwater Pump #3 to Steam Generator #4 Check Valve 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).
9B26YL00.DOC 40MIS 70
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).
9B26YL00.DOC 40MIS 71
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 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).
9B26YL00.DOC 40MIS 72
PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA)
COLD SHUTDOWN FREQUENCY JUSTIFICATION TABLE 2.1 REV 0 (2005)
PAGE 5 OF 27 Valves:
8100 8112 NO. V-CS5 Reactor Coolant Pump Seal Water Return Isolation Valve, Outside Containment 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).
9B26YL00.DOC 40MIS 73
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 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).
9B26YL00.DOC 40MIS 74
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 7 OF 27 Valves:
8107 8108 NO. V-CS7 Charging Line Isolation Valve Charging Line Isolation Valve Code Class: 2 Categorv:
B 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).
9B26YL00.DOC 40MIS 75
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 Valves:
8145 8148 NO. V-CS8 Pressurizer Auxiliary Spray Valve Pressurizer Auxiliary Spray Bypass Valve Code Class: 1 Cateeorv:
B 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).
9B26YLOO.DOC 40MIS 76
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).
9B26YL00.DOC 40MIS 77
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 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).
9B26YL00.DOC 40MIS 78
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).
9B26YL00.DOC 40MIS 79
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 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 Valves:
8809A 8809B NO. V-CS15 RHR to Cold Legs 1 &2 Isolation Valve RHR to Cold Legs 3&4 Isolation Valve Code Class: 2 Categori:
B 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 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA)
COLD SHUTDOWN FREQUENCY JUSTIFICATION TABLE 2.1 REV 0 (2005)
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 Valves:
Categorv:
8976 NO. V-CS18 RWST to Safety Injection Pumps Suction Isolation Valve Code Class: 2 B
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 Valves:
8980 NO. V-CS19 RWST to RHR Pumps Suction Isolation Valve Code Class: 2 Cateeorv:
B 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 Valves:
8703 NO. V-CS21 RHR to Hot Legs Isolation Valve Code Class: 2 Catejorv:
A 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 Valves:
8716A 8716B NO. V-CS22 RHR Train Crosstie Valves RHR Train Crosstie Valves Category:
B Function:
Code Class: 2 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 Valves:
8742A 8742B NO. V-CS23 RHR Heat Exchanger #I Discharge Check Valves RHR Heat Exchanger #2 Discharge Check Valves Code Class: 2 Catceorv:
C 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 ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA)
COLD SHUTDOWN FREQUENCY JUSTIFICATION TABLE 2.1 REV 0 (2005)
PAGE 25 OF 27 Valves:
Categorv:
Valves:
FCV-355 B
FCV-356 FCV-357 FCV-363 FCV-749 FCV-750 NO. V-CS25 Component Cooling Water Header C Isolation Valve Code Class: 3 CCW to RCP and Reactor Vessel Support Isolation Valve RCP Thermal Barrier CCW Return Isolation Valve RCP Cooler CCW Return Isolation Valve RCP Cooler CCW Return Isolation Valve 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:
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 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.
Pre-Approved per NUREG-1482 Revision 1, paragraph 3.1.1.4.
9B26YL00.DOC 40MIS
'123
PACIFIC GAS & ELECTRIC COMPANY DIABLO CANYON POWER PLANT - UNITS I & 2 INSERVICE TESTING PROGRAM PLAN - PUMPS AND VALVES ASME OM-CODE 2001 EDITION (INCLUDING 2002 AND 2003 ADDENDA)
REQUESTS FOR RELIEF FROM CODE REQUIREMENTS TABLE 2.3 REV 0 (2005)
PAGE 2 OF 2 NO. V-RR1 Valves:
CVCS-8 100 CVCS-8112 CCW-FCV-356 CCW-FCV-357 CCW-FCV-363 CCW-FCV-749 CCW-FCV-750 Code Class:
2 2
2 2
2 2
2 Category Description A
RCP Seal Water Return Isolation OC A
RCP Seal Water Return Isolation IC A
CCW to RCP's Rx Vessel Support A
RCP Thermal Barrier CCW Return OC 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:
CCW-FCV-355 Code Class:
Cateeory Description B
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 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:
Component Cooling Water Pump 1-1 Component Cooling Water Pump 1-2 Component Cooling Water Pump 1-3 Component Cooling Water Pump 2-1 Component Cooling Water Pump 2-2 Component Cooling Water Pump 2-3 Pump Type Centrifugal Centrifugal Centrifugal Centrifugal Centrifugal Centrifugal Code Class:
3 3
3 3
3 3
Group:
A A
A A
A 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 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 640F. 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-