ML18016A305

Rev 0 to HNP-IST-002, Shearon Harris Nuclear Power Plant, IST Program Plan - 2nd Interval.

ML18016A305
Person / Time
Site:	Harris
Issue date:	01/29/1998
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18016A304	List: ML18016A303 ML18016A305
References
HNP-IST-002, HNP-IST-2, NUDOCS 9802040409
Download: ML18016A305 (232)

Text

CAROLINAPOWER R LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT HNP IST Program Plan - 2nd Interval HNP-IST-002 Revision 0 9802000409 980127 qgovo<A4 PDR ADGCK 05000400 P PDR i/a~/~S

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CAROLINAPOWER Ec LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT HNP IST Program Plan -2nd Interval HNP-IST-002 Revision 0 Prepared By Date / / s Reviewed By

~~ i la,~l<s Date ANII Review Date / -'~1 Approved By Date l+-<<~ Pt~+ S~~l Ran~

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HNP-IST-002 HNP IST Program Plan - 2nd Interval LIST OF EFFECTIVE< PAGES Pages Revision Date 1 through 145 0 Revision 0 Page 2 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval TABLE OF CONTENTS e Section

1.0 DESCRIPTION

Page 4

1.1 Purpose.. 4 1.2 Regulatory Requirements . 4 1.3 Interval Information. 4 1.4 Applicable Code 5 2.0 IST PROGRAM PLAN DEVELOPMENT 5 2.1 IST Program Plan Content. 5 2.2 Selection of Components for Inclusion in IST Program Plan 5 2.3 Development of IST Program Test Requirements. ..6 2.4 System Classification.. ..6 2.5 System's and Flow Diagrams. ..6 2.6 Relief Requests ..8 2.7 Test Deferral Justifications 9

3.0 REFERENCES

4.0 PUMP IST PROGRAM .10 4.1 Scope . .10 4.2 Pump Table Format .10 4.3 Pump Table.. 12 4.4 Pump Relief Requests. .16 5.0 VALVEIST PROGRAM .17 5.1 Scope........................... ..17 5.2 Valve Table Format .18 5.3 Valve Table.. 22 5.4 Valve Relief Requests. .86 5.5 Valve Cold Shutdown Justifications. 94 5.6 Valve Refueling Outage Justifications 120 Revision 0 Page 3 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval

1.0 DESCRIPTION

1.1 Purpose This document represents the Shearon Harris Nuclear Power Plant (HNP) Inservice Testing (IST)

Program Plan for the second interval. It establishes testing requirements to assess the operational readiness of certain Safety Class 1, 2 and 3 pumps and valves that are required to:

1. Shut down the reactor to the cold shutdown condition, or

2. Maintain the reactor in the cold shutdown co'ndition, or

3. Mitigate the consequences of an'accident.

NOTE Although HNP is licensed for safe shutdown at the hot standby condition, the IST Program includes pumps and valves required to achieve and maintain the cold shutdown condition for conservatism.

This IST Program Plan provides compliance with the regulatory requirements identified in Section 1.2 (below), FSAR Section 3.9.6 and Technical Specification Surveillance Requirement 4.0.5.

h 1.2 Regulatory Requirements The Code of Federal Regulations, Title 10, Part 50.55a (10CFR50.55a), paragraph (f)(5)(i) requires each licensee of pressurized water-cooled nuclear reactors to revise the IST Program Plan to meet the requirements of 10CFR50.55a(f)(4)(ii). As a result, the IST Program Plan must be revised at 120-month intervals to comply with the requirements of the latest edition and addenda of the Code incorporated by reference in 10CFR50.55a(b) 12 months prior to the start of the 120-month interval.

1.3 Interval Information The first 120-month inter val was originally expected to be applicable for the period of May 2, 1987 through and including May 1, 1997. However, the first interval was extended to February 2, 1998 as allowed by NUREG-1482, Section 3.3.1 and ASME Section XI, 1983 Edition, Article IWA-2400(c). The NRC was notified, by letter (reference 3.12 and 3.13), of the first interval extension.

The second 120-month interval is applicable from February 2, 1998 through and including May 1, 2007.

Revision 0 Page 4 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 1.4 Applicable Code In accordance with the requirements stated in Sections 1.2 and 1.3, ASME Boiler and Pressure Vessel Code,Section XI, Division 1, 1989 Edition is the code of record for the second interval.

The Code of record, Articles IWP-1000 and IWV-1000 and Table IWA-1600-1, and 10CFR50.55a(f)(4)(viii) endorse the following OM Standards for pump and valve testing:

l. ANSI/ASME Part 1-1987, Requirements for Inservice Performance Testing of Nuclear Power Plant Pressure Relief Devices

2. ANSI/ASME Part 6- OMa - 1988 Addenda to the OM - 1987 Edition, Inservice Testing of Pumps in Light-Water Reactor Power Plants

3. ANSI/ASME Part 10- OMa - 1988 Addenda to the OM - 1987 Edition, Inservice Testing of Valves in Light-Water Reactor Power Plants All references to the "Code" made within this IST Program Plan will refer to OM Standards listed above unless otherwise specified.

2.0 IST PROGRAM PLAN DEVELOPMENT 2.1 IST Program Plan Content This IST Program Plan is comprised of two subprograms the Pump IST Program and the Valve IST Program. Both programs were developed using the information described in Sections 2.2 through 2.7. Information specific to each subprogram, such as program scope and test requirements, are presented in the section for that particular program.

Administrative and implementing procedures, reference values, test results and other records required to define and execute this IST Program Plan are retained at HNP.

2.2 Selection of Components for Inclusion in IST Program Plan Pumps and valves are selected for inclusion in the IST Program Plan based on a review of all plant systems. This review includes FSAR, Technical Specifications, Plant Operating Manual procedures, System Descriptions and flow diagrams. In accordance with 10CFR50.55a(f) and NUREG-1482, para. 2.2, this IST Program Plan is limited to ASME Class 1, 2 and 3 pumps and valves.

Revision 0 Page 5 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 2.3 Development of IST Program Test Requirements In addition to the Code, this IST Program Plan includes, as applicable, the additional requirements and recommendations of the following documents.

l. 10CFR50.55a(b)(vii)

2. Generic Letter (GL) 89-04, "Guidance on Developing Acceptable Inservice Testing Programs"

3. NUREG-1482, "Guidelines for Inservice Testing at Nuclear Power Plants"

4. NUREG/CR-6396, "Examples, Clarification, and Guidance on Preparing Requests for Relief from Pump and Valve Inservice Testing Requirements"

5. ASME Boiler and Pressure Vessel Code,Section XI, Division 1, 1989 Edition, Non-Mandatory Appendix F, Supplement 3 and 4, "Preparation of Inspection Plans" These documents and the Code provide the basis for component selection, test requirements, test frequency deferrals, relief requests, and program plan format. Relief requests and test frequency deferrals and are discussed in Sections 2.6 and 2.7.

2 4 System Classification Safety classification of pumps and valves at HNP is described in FSAR Section 3.2.2 and is shown in FSAR Table 3.2.1-1 and FSAR Figures depicting system flow diagrams. The FSAR Figure flow diagrams are equivalent to the "G>> series flow diagrams provided in the table in Section 2.5.

2.5 Systems and Flow Diagrams The following list identifies the systems contained in the Pump IST Program and Valve IST Program. This list provides a cross reference between the "S>> series simplified flow diagrams and the "G>> series flow diagrams used in determining the safety classification.

System System Name Valve ID ciS>> Series "G>> Series Acronym Flow Diagram Flow Diagram 2050 Pressurizer RC 2165-S-1301 2165-G-801 2165-S-1309 2165-G-809 2060 Chemical and Volume Control CS 2165-S-1303 2165-G-803 2165-S-1303 S01 2165-G-804 2165-S-1303 S02 2165-G-805 2165-S-1304 2165-G-807 2165-S-1305 2165-S-1307 2070 Containment Spray CT 2165-S-550 2165-G-050 2075 Post-Accident Hydrogen CM 2165-S-605 2165-G-105 SP 2165-S-1017 2165-G-517 Revision 0 Page 6 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 2.5 Systems and Flow Diagrams (Continued)

System System Name Valve ID "S" Series "G" Series Acronym Flow Diagram- Flow Diagram 2080 High Head Safety Injection SI 2165-S-1308 2165-G-808 2165-S-1310 2165-G-810 2085 Low Head Safety Injection 2165-S-1324 2165-G-824 2090 Passive Safety Injection SI 2165-S-1309 2165-G-809 2115 Reactor Coolant Sampling SP 2165-S-552 2165-G-052 2117 Post Accident Sampling SP 2165-S-552 2165-G-052 3010 Steam Generator Blowdown BD 2165-S-551 2165-G-051 3020 Main Steam MS 2165-S-542 2165-G-042 2165-S-1324 2165-G-824 3040 Auxiliary Steam AS 2165-S-689 2165-G-189 3050 Main Feedwater FW 2165-S-544 2165-G-044 3065 Auxiliary Feedwater AF 2165-S-544 2165-G-044 3070 Condensate CE 2165-S-545 2165-G-045 3100 Steam Cycle Sampling SP 2165-S-551 2165-G-051 4060 Normal Service Water SW 2165-S-547 2165-G-047 4065 Emergency Service Water SW 2165-S-547 2165-G-047 2165-S-998 S02 2168-G-498 S02 2165-S-999 S02 2168-G-499 S02 4080 Component Cooling Water CC 2165-S-1319 2165-G-819 2165-S-1320 2165-G-820 2165-S-1321 2165-G-821 2165-S-1322 2165-G-822 2165-S-1322 S01 2165-G-822 So 1 4085 Essential Service Chilled Water CH 2165-S-998- 2168-G-498 SW 2165-S-998 S02 2168-G-498 S02 2165-S-998 S03 2168-G-498 S03 2165-S-998 S04 2168-G-499 2165-S-999 2168-G-499 S02 2165-S-999 S02 2168-G-499 S03 2165-S-999 S03 2165-S-999 S04 4115 Emergency Screen Wash SC 2165-S-808 2165-G-308 5100 Emergency Diesel Generator Fuel DF 2165-S-563 2165-G-063 Oil Supply 2165-S-633 S03 2165-G-133 5112 Emergency Diesel EA 2165-S-633 S04 2165-G-133 Air Generator'tarting 6135 Instrument Air IA 2165-S-801 2165-G-301 2165-S-1017 2165-G-517 6140 Service Air SA 2165-S-800 2165-G-300 2165-S-998 S02 2168-G-498 S02 2165-S-999 S02 2168-G-499 S02 Revision 0 Page 7 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 2.5 Systems and Flow Diagrams (Continued)

System System Name Valve ID "S" Series "G" Series Acronym Flow Diagram Flow Diagram 6175 Site Fire Protection FP 2165-S-888 2165-G-388 6240 Radioactive Equipment Drains ED 2165-S-685 2165-G-185 2165-S-1313 2165-G-813 6270 Demineralized Water DW 2165-S-799 2165-G-299 7005 Radiation Monitoring SP 2165-S-605 2165-G-105 7110 Spent Fuel Pool Cooling SF 2165-S-561 2165-G-061 2165-S-805 2165-G-305 8060 Containment Vacuum Breakers CB 2165-S-1017 2168-G-517 2166-B-431 DP38 FSAR Tbl. 6.2.4-1 8070 Containment Pressurization LT 2166-S-916 2165-G-416 8170 Containment Purge CP 2165-S-1017 2168-G-517 2166-B-431 DP39 FSAR Tbl. 6.2.4-1 8210 HVAC Auxiliary Building AV 2165-S-1017 2168-G-517 S03 CZ 2168-G-517 S05 8220 HVAC Control Room Area 2165-S-1017 2168-G-517 S04 8352 HVAC Fuel Handling Building FV 2165-S-1017 2168-G-533 2.6 Relief Requests Specific requests for relief are included in accordance with 10CFR50.55a(a)(3), (f)(5) and (f)(6).

Where conformance with the requirements of the Code have been determined to be impractable, alternate testing is proposed that would provide an acceptable level of quality and safety. Where conformance with the requirements of the Code would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety, alternate testing is proposed that would provide useful information to assess the operational readiness of the component tested.

The relief requests define the component(s) and test(s) involved, the basis for relief, the proposed alternate testing and the status of the NRC evaluation in accordance with 10CFR50.55a(f)(4)(iv).

Pump relief requests are located after the Pump Table and valve relief requests are located after the Valve Table.

Relief requests are numbered in a "XX-YRN"format where:

= System Acronym

= PR for pumps and VR for Valves

= Unique sequential number (e.g., SI-VR2 would be the second relief request for valves in the safety injection system)

Revision 0 Page 8 of 145

0 w

HNP-IST-002 HNP IST Program Plan - 2nd Interval 2.7 Test Deferral Justifications In accordance with paragraphs 4.2.1.2 and 4.3.2.2 of Part 10 of the Code, certain valves are full stroke exercised during cold shutdown conditions when the valve cannot be exercised during normal operation. When the valve cannot be exercised during cold shutdown conditions, then the valve is full stroke exercised during refueling outages. The technical justification for exercising a valve during cold shutdown or refueling outages rather than normal operation is provided in a Cold Shutdown Justification or Refueling Outage Justification.

Valves tested during cold shutdowns or refueling outages shall be scheduled in accordance with paragraphs 4.2.1.2 and 4.3.2.2 of Part 10 of the Code.

Cold Shutdown Justifications and Refueling Outage Justifications are numbered in a "XX-YYJN" format where:

XX = System Acronym YYJ = CSJ for Cold Shutdown Justifications, ROJ for Refuel Outage Justifications N = Unique sequential number (e.g., SI-CSJ2 would be the second cold shutdown justification for valves in the safety injection system)

3.0 REFERENCES

1. Code of Federal Regulations, Title 10, Part 50, Section 55a and Appendix J

2. ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition

3. ANSI/ASME OM 1987- Part 1, Requirements for Inservice Performance Testing of Nuclear Power Plant Pressure Relief Devices

4. ANSI/ASME OM 1988a - Part 6, Inservice Testing of Pumps in Light-Water Reactor Power Plants

5. ANSI/ASME OM 1988a - Part 10, Inservice Testing of Valves in Light-Water Reactor Power Plarits

6. HNP Technical Specifications, Surveillance Requirement 4.0.5

7. SHNPP Final Safety Analysis Report, Section 3.2.2, System Quality Group Classifications

8. SHNPP Final Safety Analysis Report, Section 3.9.6, Inservice Testing of Pumps and Valves

9. NRC NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants

10. Generic Letter (GL) 89-04. Guidance on Developing Acceptable Inservice Testing Programs

11. NUREG/CR-6396, "Examples, Clarification, and Guidance on Preparing Requests for Relief from Pump and Valve Inservice Testing Requirements Revision 0 Page 9 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval

3.0 REFERENCES

(Continued)

12. HNP Letter 97-073, dated April 4, 1997, "Extension of 1st Ten- Year ISI/IST Program Interval

13. HNP Letter 97-177, dated September 2, 1997, "Extension of'1st Ten-Year ISI/IST Program Interval

14. ISI-800, Inservice Testing of Pumps

15. ISI-801, Inser vice Testing of Valves

16. ISI-802, Inservice Testing of Pressure Relief Devices 4.0 PUMP IST PROGRAM A

4.1 Scope The Pump IST Program establishes testing requirements to assess the operational readiness of those Safety Class 2 and 3 centrifugal pumps provided with an emergency power source that are required to:

1. -

Shut down the reactor to the cold shutdown condition, or

2. Maintain the reactor in the cold shutdown condition, or

3. Mitigate the consequences of an accident.

Excluded from the above are:

1. Drivers, except where the pump and driver form an integral unit and the pump bearings are in the driver; .

2. Pumps supplied with emergency power solely for operating convenience.

The IST Pump Program is implemented by HNP administrative procedure ISI-800 "Inservice Testing of Pumps".

4.2 Pump Table Format A complete list of pumps in the scope of the Pump IST Program is provided on the following pages in a tabular format. The Pump Table is sorted alpha-numerically by pump number. A description of each column in the Pump Table is shown below with applicable abbreviations.

Pump Number Unique alpha-numeric designator assigned to each pump. The pump number used in the Pump Table is a combination of an abbreviation of the pump name and designator shown on the "S" and "G".series flow diagrams Revision 0 Page 10 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 4.2 Pump Table Format (Continued)

Nomenclature Descriptive name of the pump.

Drawing Simplified flow diagram which the pump is located. A complete list of flow diagrams is provided in Section 2.5.

Dwg Coord Drawing coordinate of pump location on the simplified flow diagram.

Safety Class Safety class of the pump as shown on FSAR Section 3.2.2 and "G" series flow diagrams. Section 2.4 provides additional information concerning safety classification.

Pump Type Pump design.

C-H Centrifugal pump where orientation of the pump and motor shafts in the horizontal plane C-V Centrifugal pump where orientation of the pump and motor shafts in the vertical plane VLS Centrifugal vertically suspended pump where the pump driver and pumping element are connected by a line shaft within an enclosing column which contains the pump bearings.

Speed Identifies whether the pump speed is fixed or variable. All pumps in the IST Program operate at speeds greater than 600 rpm.

Fixed Speed is constant and is a function of the motor design Vari Speed is variable depending on steam input to the terry turbine Test Type Parameters measured and evaluated during the pump test.

dP Pump differential pressure Q Pump flow N Pump speed (variable speed pumps only)

Vv Pump vibration velocity (broad band unfiltered peak in inches per second) measured at the locations defined per OM-6, para. 4.6.4.

Test Freq Frequency of pump testing per OM-6.

Q Quarterly (once per 92 days)

Relief Request Reference to applicable relief request. Pump relief requests are located in Section 4.4 following the Pump Table.

Remarks Applicable notes or other unique comments that provide clarification.

referenced in the Remarks column are located at the end of the Pump All'otes Table.

Revision 0 Page 11 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 4.3 Pump Table Pump Number Nomenclature Dwg ~ Safety Pump Speed " Test I Test Relief Remarks tCoord,',, Class Type Type .',

'req I Request; AFIA-SA MD Auxiliary Feedwater Pump 2165-S-544 M-5 3 C-H Fixed dP n/a Note 1 II All I

Q AF-PRI Vv n/a AFIB-SB MD Auxiliary Feedwater Pump 2165-S-544 M-8 3 C-H Fixed dP Q n/a Note 1 I Bll It Q Q AF-PRI Vv Q n/a AFIX-SAB TD Auxiliary Feedwater Pump 2165-S-544 M-10 3 C-H Vari dP Q n/a Note I IX-SAB N Q n/a Q Q n/a Vv Q n/a BA]A-SA. Boric Acid Transfer Pump "IA" 2165-S-1307 D-8 2 C-H Fixed dP Q n/a Note 2 Q Q n/a Vv Q n/a BAIB-SB Boric Acid Transfer Pump "I B" 2165-S-1307 6-8 2 C-H Fixed dP Q n/a Note 2 Q Q n/a Vv Q n/a-CCW I A-SA Component Cooling Water Pump 2165-S-1319 F-7 3 C-H Fixed dP Q n/a Note 3 I All II Q Q n/a Vv Q n/a CCWI B-SB Component Cooling Water Pump 2165-S-1319 L-7 3 C-H Fixed dP Q n/a Note 3 I BII

~ I Q Q n/a Vv Q n/a CCWI C-SAB Component Cooling Water Pump 2165-S-1319 1-7 3 C-H Fixed dP Q n/a Note 3 II I Ctt n/a Q Q Vv Q n/a CTI A-SA Containment Spray Pump "A" 2165-S-550 F-8 2 C-V Fixed dP Q n/a Note 4 Q Q n/a Vv Q n/a Revision 0 Page 12 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 4.3 Pump Table Pump Number Nomenclature Drawing Dwg "Safety. Pump T

Speed Test, Test 'elief Remarks Coo rd Class Type Type Freq Request CTI B-SB Containment Spray Pump "B" 2165-S-550 L-8 2 C-V Fixed dP Q n/a Note 4 Q Q n/a Vv Q n/a DFOI A-SA D.G. Fuel Oil Transfer Pump "IA" 2165-S-563 F-2 3 C-H Fixed dP Q n/a None Q Q n/a Vv Q n/a DFOI B-SB D.G. Fuel Oil Transfer Pump "IB" 2165-S-563 F-7 3 C-H Fixed dP Q n/a None Q Q n/a Vv Q n/a ESWI A-SA Emergency Service Water Pump 2165-S-547 C-2 3 VLS Fixed dP Q n/a Note 5 II I All Q Q n/a Vv Q n/a ESWI B-SB Emergency Service Water Pump 2165-S-547 C-3 3 VLS Fixed dP Q n/a Note 5 II I Blt Q Q n/a Vv Q n/a ESWSW I A-SA Emergency Screenwash Pump 2165-S-808 C-15 3 C-H Fixed dP Q n/a None I AII II Q Q n/a Vv Q n/a ESWSWI B-SB Emergency Screenwash Pump 2165-S-808 C-12 3 C-H Fixed dP Q n/a None

~ I Bll 1

Q Q n/a Vv Q n/a FPCIA-SA Spent Fuel Pool Cooling Pump 2165-S-805 G-10 3 C-H Fixed dP Q n/a None IIAII Q Q n/a Vpih Q n/a Vv Q n/a FPCI B-SB Spent Fuel Pool Cooling Pump 2165-S-805 K-10 3 C-H Fixed dP Q n/a None IIBII Q Q n/a Vv Q n/a Revision 0 Page 13 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 4.3 Pump Table t

ll Dwg 1Safety Pump 'pccd I Test Test Relief Remarks Pump Number Nomenclature I

",Coord I Class Type Type Freq ', Request

,'41A-SA Chilled Water Pump "IA" S02 I-j 3 '165-S-998 C-H Fixed dP Q n/a None Q Q n/a Vv Q n/a P41B-SB Chilled Water Pump "IB" 2165-S-999 S02 1-7 3 C-H Fixed dP n/a None Q n/a Vv Q n/a RHRI A-SA Residual Heat Removal Pump -2165-S-1324 L-11 2 C-V Fixed dP Q n/a Note 4 HI All n/a Q Q Vv n/a RHRI B-SB Residual Heat Removal Pump 2165-S-1324 I-l I 2 C-V Fixed dP n/a Note 4 II BI~

I Q Q n/a Vv n/a SI1A-SA Charging/Safety Injection Pump 2165-S-1305 H-9 2 C-H Fixed dP n/a Note 6 (CSIP) "IA" Q Q n/a Vv Q n/a SII B-SB Charging/Safety Injection Pump 2165-S-1305 J-9 2 C-H Fixed dP Q n/a Note 6 (CSIP) "I B" Q Q n/a Vv Q n/a SI IC-SAB Charging/Safety Injection Pump 2165-S-1305 K-9 2 C-H Fixed dP Q n/a Note 6 (CSI P) "IC" Q Q n/a Vv Q n/a SWBI A-SA Emergency Service Water Booster 2165-S-547 G-5 3 C-H Fixed dp Q n/a None Pump "IA" Q Q n/a Vv Q n/a SWBI B-SB Emergency Service Water Booster 2165-S-547 G-14 3 C-H Fixed dP Q n/a None Pump "I B" Q Q n/a Vv Q n/a Revision 0 Page 14 of 145

0 HNP-IST-002 HNP IST Program Plan - 2nd Interval 4.3 Pump Table Notes The following notes provide clarification to the method of testing applied to the associated pump and are included by reference in the Pump Listing column "Remarks".

1. Quarterly pump testing will be accomplished utilizing the small diameter recirculation line back to the CST. Full flow testing will be performed prior to plant cooldown.

2. This small centrifugal pump does not have bearings in the pump casing. The pump impeller is attached to the motor shaft. Therefore, vibration measurements will be taken on the inboard motor bearing housing in a plane approximately perpendicular to the rotating shaft in two orthogonal directions. In addition, vibration measurements will be taken in the axial direction on the motor thrust bearing. Ranges for vibration parameters will be in accordance with OM-6, Table 3a for centrifugal pumps >600 rpm. Ranges for hydraulic parameters will be in accordance with OM-6, Table 3b for centrifugal pumps.

3. Any one of the three CCW pumps may function as an installed spare. One pump is normally running, the second is aligned as an automatic backup to the operating pump, and the third pump is electrically disconnected. In the event of a failure of the operating pump, the second (reserve) pump automatically starts upon detection of low CCW header pressure. The installed spare is electrically connected to the opposite emergency bus from the now operating (reserve) pump and placed in a standby reserve condition. The installed spare is required to be tested only when it is connected to the system.

4. This vertical centrifugal pump does not have bearings in the pump casing and does not fit the definition of a vertical line shaft pump. The pump impeller is attached to the motor shaft. Therefore, vibration measurements will be taken on each motor bearing housing in a plane approximately perpendicular to the rotating shaA in two orthogonal directions. In addition, vibration measurements will be taken in the axial direction on the motor thrust bearing. Ranges for vibration parameters will be in accordance with OM-6, Table 3a for centrifugal pumps t600 rpm. Ranges for hydraulic parameters will be in accordance with OM-6, Table 3b for centrifugal pumps.

5. Pump differential pressure is calculated using pump bay level and discharge pressure. The bay level and discharge pressure will be measured after two minutes of operation at test conditions as stable as the system permits.

6. Any one of the three CSIPs may function as an installed spare. One pump is normally running, the second is aligned as an automatic backup to the operating pump, and the third pump (normally "IC") is electrically disconnected. In the event of a failure of the operating pump, the second (reserve) pump automatically starts, and the installed spare is electrically connected to the opposite emergency bus from the now operating (reserve) pump and placed in a standby reserve condition. The installed spare is required to be tested only when it is connected to the system.

Revision 0 Page 15 of 145

0 HNP-IST-002 HNP IST Program Plan - 2nd Inteval 4.4 Pump Relief Requests AF-PR1 Com onent Dwg System Description Flow Diagram ID Coord AF1A-SA MD Auxiliary Feedwater Pump "1A" 2165-S-544 M-5 3065 AF1B-SB MD Auxiliary Feedwater Pump "1B" 2165-S-544 M-8 3065 Code Test Requirements The full scale range of each analog instrument shall not be greater than three times the reference value [OM-6, Para.

4.6.1.2(a)].

Basis for Relief:

The permanently installed flow instrument which is utilized to conduct the quarterly pump tests of the two motor driven auxiliary feedwater pumps (AF1A-SA and AF1B-SB) has a calibrated full scale range which exceeds a factor of three times their reference values. The full scale range of the instrument, FI-2172, is 0-200 gpm while the reference value of each pump is 51 gpm. FI-2172 is installed in a common pump recirculation line which is shared by both the two motor driven AFW pumps and the single turbine driven AFW pump. The indicator is sized to accommodate the combined restricted flows of all three pumps simultaneously. Although the full scale range of FI-2172 does not comply with Code requirements, its accuracy of +1% of full scale exceeds that which is required.

Even though FI-2172 does not meet the Code requirement for range, it is capable of providing an indicated accuracy at the reference value that is superior to the minimum indicated accuracy that would be required by the Code. Based on the least accurate instrument that would theoretically be allowed by the Code, the minimum required indicated accuracy is +6%.

(This fact is documented by NUREG-1482, paragraph 5.5.1.) The indicated accuracy of FI-2172, as derived based upon the current reference values, is as follows:

Reference value = 51 gpm Full scale range = 200 gpm Instrument tolerance = +2 gpm (+1% x 200 gpm)

Therefore the indicated accuracy is:

+2 gpm /51 gpm x 100% = +3.9%

As demonstrated, the iridicated accuracy of FI-2172 is better than that which is theoretically allowed by the Code.

Alternate Test The existing permanently installed pump instrument is acceptable because the indicated accuracy is less than or equal to

+6% as calculated at the reference value. No alternate testing or instrumentation will be utilized.

Approval Status NRC approval of this relief request is pending and may not be used until NRC approval is granted.

Revision 0 Page16 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.0 VALVEIST PROGRAM The Valve IST Program establishes testing requirements to assess the operational readiness of those Safety Class 2 and 3 valves and pressure relief devices.

The active or passive Safety Class 1, 2, and 3 valves included are those that are required to perform a specific function in:

1. Shutting down the reactor to the cold shutdown condition, or

2. Maintaining.the reactor in the cold shutdown condition, or

3. Mitigating the consequences of an accident.

The Safety Class 1, 2, and 3 pressure relief devices included are those protecting systems or portion of systems that perform a specific function in:

1. Shutting down the reactor to the cold shutdown condition, or

2. Maintaining the reactor in the cold shutdown condition, or

3. Mitigating the consequences of an accident.

The following are excluded from above, provided that they are not required to perform a specific function as specified above:

1. Valves used only for operating convenience such as vent, drain, instrument, and test valves.

2. Valves used only for system control, such as pressure regulating valves.

3. Valves used only for system or component maintenance.

4. External control and protection systems responsible for sensing plant conditions and providing signals for valve operation.

Exclusion Exceptions Valves equipped with position indication or fail-safe mechanisms are tested for that specific function.

The IST Valve Program Plan is implemented by HNP.administrative procedures ISI-801 "Inservice Testing of Valves" and ISI-S02 "Inservice Testing of Pressure Relief Devices".

Revision 0 Page 17 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval ~

5.2 Valve Table Format A complete list of valves in the scope of the Valve IST Program is provided on the following pages in a tabular format. The Valve Table is sorted alpha-numerically by valve number as read left to right by character. A description of each column in the Valve Table is shown below with applicable abbreviations.

Valve Number Unique alpha-numeric designator assigned to each valve. The valve number used in the Valve Table is taken from the "S" flow diagram. A correlation between the different valve numbers on the "S" and "G" series flow diagrams is provided in the plant Electronic Data Base System (EDBS).

Nomenclature Descriptive name of the valve.

Drawing Simplified flow diagra'm which the valve is located. A complete list of flow diagrams is provided in Section 2.5.

Dwg Coord Drawing coordinate of valve location on the simplified flow diagram.

System Unique number designator assigned to each system. Numbers for the different systems used in the Valve Listing are defined in Section 2.5.

Size (inch) Valve size, in inches, as defined by the "G" series drawings and EDBS.

Body Valve design body style.

3W Three-way valve BA Ball valve BF Butterfly valve CK Check valve KFC Excess flow check valve DA Diaphragm valve GA Gate valve GL Globe valve PL Plug valve RD Rupture Disc RV Relief valve Actuator Actuator type used to change valve obturator position.

AO Air operator EH Electro-hydraulic operator MAN Manual operator MO Motor operator SA Self actuated SO Solenoid operator Revision 0 Page 18 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.2 Valve Table Format (Continued)

Safety Class Safety class of the pump as shown on FSAR Section 3.2.2 and "G" series flow diagrams. Section 2.4 provides additional information concerning safety classification.

OM Cat ASME Code category as defined in OM-10, Para. 1.4 A Valves for which seat leakage is limited to a specific amount in the closed position for fulfillment of their required function(s).

A/C Valves which are both self actuating and for which seat leakage is limited to a specific amount in the closed position for fulfillment of their required function(s).

B Valves for which seat leakage in the closed position is inconsequential for fulfillment of the required function(s).

C Valves which are self-actuating in response to some system characteristic, such as pressure (relief valves) or flow direction (check valves) for fulfillmentof the required function(s).

D Valves which are actuated by an energy source capable of only one operation such as rupture disks or explosively actuated valves.

Act/Pass Identifies whether the valve performs an active or passive safety function as defined by OM-10 para. 1.3, determined by review of the FSAR and operating procedures.

Act Active valve Pass Passive valve Norm Pos Identifies the valve position during normal plant operation as defined by plant operating procedures.

C Closed LC Locked Closed LO Locked Open LT Locked Throttled 0 Open 0/C Open and Closed T Throttled Revision 0 Page 19 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.2 Valve Table Format (Continued)

Safety Pos, Identifies the valve position required for the valve to perform its safety function.

C Closed 0 Open 0/C Open and Closed T Throttled Fail Pos Identifies the position of the valve on loss of actuator power.

AI As-Is C Closed 0 Open n/a Not applicable. Valve does not have a fail position Test Type Identifies the test requirements which apply to the valve as determined by OM-10 Section 4.

DIS Valve will be disassembled and visually inspected in accordance with OM-10, Para. 4.3.2.4(c) as described in the applicable. refueling outage justification.

FSC Fail stroke closed, exercise valve with a fail-safe actuator to the closed position in accordance with OM-10, Para. 4.2.1.6.

FSO Fail'stroke open exercise valve with a fail-safe actuator to the open position in accordance with OM-10, Para. 4.2.1.6.

LJ Leak test per Appendix J, Type C, in accordance with OM-10, Para.

4.2.2.2 (containment isolation function only).

LK Leak test per OM-10, Para. 4.2.2.3 (leakage rate for other than containment isolation valves).

PIT Valve with remote position indication verified in accordance with OM-10, Para. 4.1.

PSC Partial stroke close exercise in accordance with OM-10, Para. 4.2.1.2 and 4.3.2.2.

PSO Partial stroke open exercise in accordance with OM-10, Para. 4.2.1.2 and 4.3.2.2.

SC Stroke close exercise valve for operability in accordance with OM-10, Para. 4.2.1.

SDIS Valve will be disassembled and visually inspected as described in the Relief Request and as outlined in the IST Program text.

Revision 0 Page 20 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.2 Valve Table Format (Continued)

SKID Testing'of the associated major component is verifies the operational readiness of the skid-mounted and component subassemblies.

SO Stroke Open exercise valve for operability in accordance with OM-10, Para. 4.2.1.

SP Relief Valve in accordance with OM-10, Para. 4.3.1 and OM-I.

STC Stroke time closed valve in accordance with OM-10, Paras. 4.2.1.4 and 4.2.1.8.

STO Stroke time open valve in accordance with OM-10, Paras. 4.2.1.4 and 4.2.1.8.

Test Freq Identifies the frequency required for valve testing as determined by OM-10.

Q Quarterly, Once per 92 days CS Cold Shutdown, Testing performed during the cold shutdown condition (ifnot performed during the previous 92 days) in accordance with OM-10, Para. 4.2.1.2 and 4.3.2.2. Ifrequired, testing may be performed during the transition period between normal operation and cold shutdown.

RO Refueling Outage, Testing performed during the refueling outage condition in accordance with OM-10, Para. 4.2.1.2 and 4.3.2.2. If required, testing may be performed during the transition period between normal operation and refueling.

6NIO Set Point testing, Tested during the time period defined in OM 1987 (overpressure protection devices) 2YR Leak testing per OM-10, Para. 4.2.2.3 or Position indication verification per OM-10, Para. 4.1.

5YR Set Point testing, Tested during the time period defined in OM 1987 (overpressure protection devices) 10YR Set Point testing, Tested during the time period defined in OM 1987 (overpressure protection devices)

CS J/RO J/RR This field identifies, by unique number, any cold shutdown test justification (CS 1), refueling outage test justification (ROJ) or relief request (RR) that may be associated with the individual component. These documents are located after the Valve Table in Sections 5.4, 5.5 and 5.6.

Revision 0 Page 21 of 145

t 4

e HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve Nomenclature Flow Diagram )

wg System '* Body l Actuator 0M [Act/ Norm Safety Fail, Test; Test 'SJ/ROJ Number Coord (Inch) Class Cat Pass Pos Pos Pos Type Freq, RR

] J j IAF-102 FW "B" Preheater Bypass 2165-S-544 F-5 3065 6 GA AO 2 B Act 0 C FSC CS AF-CSJ I Iso Vlv (CIV) PIT 2YR n/a STC CS AF CSJ I I AF-103 FW "B" Preheater Bypass 2165 S 544 G 5 3065 6 CK SA 2 C Act 0 C n/a SC RO AF-ROJ I Check Vlv I AF-106 SG "B" AFW Injection 2165-S-544 G-2 3065 6 CK SA 2 C Act 0 0 n/a SO n/a Check Vlv I AF-110 Turbine Driven AFWP 2165-S-544 N- I I 3065 2 CK SA 3 C Act C 0 n/a SO Q n/a Recirc Line Check Vlv I AF-117 Turbine Driven AFWP 2165-S-544 L-10 3065 6 CK SA 3 C Act C 0 n/a SO CS AF-CSJ5 Discharge Line Check Vlv I AF-129 TD AFWP Flow Control 2165-S-544 J 9 3065 4 GL EH 3 B Act 0 0/C 0 FSO Q n/a Vlv to SG "A" PIT 2YR n/a STC Q n/a STO Q n/a I AF-130 TD AFWP Flow Control 2165-S-544 J-IO 3065 4 GL EH 3 B Act 0 0/C 0 FSO .

Q n/a Vlv to SG "B" PIT 2YR n/a STC Q n/a STO Q n/a I AF-131 TD AFWP Flow Control 2165-S-544 J-11 3065 4 GL EH 3 B Act 0 0/C 0 FSO Q n/a Vlv to SG "C" PIT 2YR n/a STC. Q . n/a STO Q n/a I AF-136 TD AFWP Discharge Line 2165-S-544 G-6 3065 4 CK SA 3 C Act 0 n/a SO CS AF-CSJS Check Vlv to SG "A" I AF-137 TD AFWP Iso Vlv to SG 2165 S 544 G 6 3065 4 GA MO 2 B Act 0 0/C AI PIT 2YR n/a "A"(CIV) STC Q n/a STO Q n/a I AF-142 TD AFWP Discharge Line 2 I 65-S-544 H-9 3065 4 CK SA 3 C Act C 0 n/a SO CS AF-CSJ5 Check Vlv to SG "B" Revision 0 Page22 of 145

HNP-IST-002 HNP IST Program Plan -2nd Interval 5.3 Valve Table Nomenclature Flow Diagram I "g System I . Body Safety,'M Act / Norm 'Safety Fail 'est Test CSJ/ROJ Number Coord (inch) I Class~ CatIPass" Pos, Pos Pos Type Freq RR

]

ii L

IAF-143 TD AFWP Iso Vlv to SG 2165-S-544 H-8 3065 4 GA MO 2 B Act 0 0/C AI PIT 2YR n/a "B"(CIV) STC Q n/a STO Q n/a I AF-148 TD AFWP Discharge Line 2165-S-544 G-8 3065 4 CK SA 3 C Act C 0 SO CS AF-CSJ$

Check Vlv to SG "C" 1AF-149 TD AFWP Iso Vlv to SG 2165-S-544 G-8 3065 4 GA MO 2 B Act 0 0/C AI PIT 2YR n/a "C"(CIV) STC Q n/a STO Q n/a I AF-153 "A" SG Ammonia Addition 2165-S-544 B4 3065 I GL AO 2 B Act 0/C C FSC n/a Q

to AFW Iso Vlv (CIV) PIT 2YR n/a STC Q n/a 1AF-155 "A" SG Hydrazine Addition 2165-S-544 B-3 3065 I GL AO 2 B Act 0/C C FSC Q n/a to AFW Iso Vlv (CIV) PIT 2YR n/a STC Q n/a I AF-157 "B" SG Ammonia Addition 2165-S-544 G-4 3065 I GL AO 2 B Act 0/C C C FSC Q n/a to AFW Iso Vlv (CIV) PIT 2YR n/a STC Q n/a I AF-159 "B" SG Hydrazine Addition 2165-S-544 G-3 3065 I GL AO 2 B Act 0/C C FSC Q n/a to AFW Iso Vlv (CIV) PIT 2YR n/a STC Q n/a IAF-16 AFWP "IA"Discharge 2165-S-544 L-6 3065 4 CK SA 3 C Act C 0/C n/a SC CS AF-CSJ2 Line Check Vlv SO CS AF-CSJ2 I AF-161 "C" SG Ammonia Addition 2165-S-544 K-4 3065 I GL AO 2 B Act 0/C C FSC n/a Q

to AFW Iso Vlv (CIV) PIT 2YR n/a STC Q n/a I AF-163 "C" SG Hydrazine Addition 2165-S-544 K-3 3065 I GL AO 2 B Act 0/C C FSC Q n/a to AFW Iso Vlv (CIV) PIT 2YR n/a STC Q n/a IAF-19 AFWP "1A" Pressure 2165-S-544 K-6 3065 4 GL EH 3 B Act T 0 0 FSO CS AF-CSJ3 Control Vlv PIT 2YR n/a STO CS AF-CSJ3 Revision 0 Page23 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve i Nomenclature Flow Diagram Dwg 'System 1,

Size l Body iActuatorl'SafetylOM Act/ Norm Safety Fail l Test Test CSJ/ROJ Number <Coosd( (sash)~ Class Cat Pass Pos Pos Pos )Type Freq RR

[ [

IAF-201 MD AFWP Discharge Line 2165-S-544 H-5 3065 4 CK SA 3 C Act C 0/C n/a SC Q n/a Check Vlv to SG "A" SO CS AF-CSJ4 IAF-202 MD AFWP Discharge Line 2165-S-544 1-8 3065 4 CK SA 3 C Act C 0/C n/a SC Q n/a Check Vlv to SG "B" SO CS AF-CSJ4 I AF-203 MD AFWP Discharge Line 2165-S-544 I 6 3065 4 CK SA 3 C Act C 0/C SC Q n/a Check Vlv to SG "C" SO CS AF-CSJ4 I AF-204 TD AFWP Discharge Line 2165-S-544 H7 3065 4 CK SA 3 C Act C 0/C n/a SC Q n/a Check Vlv to SG "A" SO CS AF-CSJ5 I AF-205 TD AFWP Discharge Line 2165-S-544 H-10 3065 4 CK SA 3 C Act C 0/C SC Q n/a Check Vlv to SG "B" SO CS AF-CSJ5 I AF-206 TD AFWP Discharge Line 2165-S-544 H-11 3065 4 CK SA 3 C Act C 0/C SC Q n/a Check Vlv to SG "C" SO CS AF-CSJ5 I AF-23 AFWP "IB" Recirc Line 2165-S-544 N9 3065 2 CK SA 3 C Act C 0 n/a SO Q n/a Check Vlv I AF-31 AFWP "IB" Discharge Line 2165-S-544 L8 3065 4 CK SA 3 C Act C 0/C n/a SC CS AF-CSJ2 Check Vlv SO CS AF-CSJ2 I AF-34 AFWP "IB" Pressure 2165-S-544 K-8 3065 4 GL EH 3 B Act T 0 0 FSO CS AF-CSJ3 Control Vlv PIT 2YR n/a STO CS AF-CSJ3 IAF-4 AFWP "IA"Recirc Line 2165-S-544 N-6 3065 2 CK SA 3, C Act C 0 n/a SO Q n/a Check Vlv I AF-49 AFWP "IAE IB" Flow 2165-S-544 J 6 3065 4 GL EH 3 B Act 0 0/C 0 FSO Q n/a Control Vlv to SG "A" PIT 2YR n/a STC Q n/a STO Q n/a IAF-50 AFWP "IA & I B" Flow 2165-S-544 J-7 3065 4 GL EH 3 B Act 0 0/C 0 FSO Q n/a Control Vlv to SG "C" PIT 2YR n/a STC Q n/a STO Q n/a Revision 0 Page24 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve Number Nomenclature Flow Diagram ICoord System j Size

',(inch) "

'ody Actuator SafetylOM Act/>> Norm 'tSafety', Fail Class l~

Cat ( Pass i Pos Pos I Pos i

Test Test

'ype Freq CSJ/ROJ RR I AF-51 AFWP "IA& IB" Flow 2165-S-544 J-8 3065 4 GL EH 3 B Act 0 0/C C FSO Q n/a Control Vlv to SG "B" PIT 2YR n/a STC Q n/a STO Q n/a IAF-54 MD AFWP Discharge Line 2165-S-544 G-6 3065 4 CK SA 3 C Act C 0 SO CS AF-CSJ4 Check Vlv to SG "A" I AF-55 AFWP "IA& IB" Iso Vlv 2165-S-544 G-6 3065 GA MO B Act 0 0/C AI PIT 2YR n/a to SG "A" (CIV) STC Q n/a STO Q n/a IAF-64 FW "A" Preheater Bypass 2165-S-544 C-6 3065 GA AO 2 B Act 0 FSC CS AF-CSJ I Iso Vlv (CIV) PIT 2YR n/a STC CS AF-CSJ I I AF-65 FW "A" Preheater Bypass 2165-S-544 C-6 3065 6 CK SA 2 C Act 0 C n/a SC RO AF-ROJ I Check Vlv I AF-68 SG "A" AFW Injection 2165-S-544 C-2 3065 6 CK SA 2 C Act 0 0 n/a SO Q n/a Check Vlv I AF-73 MD AFWP Discharge Line 2165-S-544 H-7 3065 4 CK SA 3 C Act C 0 n/a SO CS AF CSJ4 Check Vlv to SG "C" I AF-74 AFWP "IA& IB" Iso Vlv 2165-S-544 G-7 3065 4 GA MO -

2 B Act 0 0/C Al PIT 2YR n/a to SG "C" (CIV) STC Q n/a STO Q n/a I AF-81 FW "C" Preheater Bypass 2165-S-544 E-7 3065 6 GA AO 2 B Act 0 C FSC CS AF-CSJ I Iso Vlv (CIV) PIT 2YR n/a STC CS AF-CSJ I I AF-84 FW "C" Preheater Bypass 2165-S-544 E-5 3065 6 CK SA 2 C Act 0 C n/a SC RO AF-ROJ I Check Vlv I AF-87 SG "C" AFW Injection 2165-S-544 K-2 3065 6 CK SA C Act 0 0 n/a SO Q n/a Check Vlv I AF-92 MD AFWP Discharge Line 2165-S-544 1-8 3065 4 CK SA 3 C Act C 0 n/a SO CS AF CSJ4 Check Vlv to SG "B" Revision 0 Page25 of 145

HNP-IST-002 HNP IST Program Plan - 2ntl Interval 5.3 Valve Table Valve Nomenclature Flow Diagram Dwg System B d A t to Safety OM'Act/ Norm',,Safety Fail Test Test CSJ/ROJ Number Coord (inch) Class Cat Pass Pos .

Pos Pos Type Freq RR I AF-93 AFiVP "IA& IB" Iso Vlv 2165-S-544 H-8 3065 4 GA MO 2 B Act 0 0/C AI PIT 2YR n/a to SG "B" (CIV) STC Q n/a STO Q n/a I AS-344 Auxiliary Steam Excess 2165-S-689 K-14 3040 CK SA 3 C Pass 0 n/a n/a DIS RO n/a Flow Check Vlv I AS-345 Auxiliary Steam Excess 2165-S-689 K-14 3040 I CK SA 3 C Pass n/a n/a DIS RO n/a Flow Check Vlv IAV-I Filter Train Inlet Iso Vlv 2165-S-1017 8210 20 BF MO B Act C 0 Al PIT 2YR n/a From RAB to Emergency STO Q n/a Exhaust Fan "A" I AV-11 RAB Switchgear Rm "A" 2165-S-1017 B-11 8210 42 BF MO B Pass C C Al PIT 2YR n/a Smoke Purge Exhaust Iso Vlv I AV-12 RAB Switchgear Rm "B" 2165-S-1017 E-11 8210 24 BF MO 3 B Pass C C Al PIT 2YR n/a Rod Control Cabinet Rm Smoke Purge Exhaust Iso Vlv I AV-13 RAB Switchgear Rm "B" 2 I 65-S-1017 D-I I 82 I 0 42 BF MO 3 B Pass C C AI PIT 2YR n/a Smoke Purge Exhaust Iso Vlv I AV-2 Inlet Iso Vlv From RAB to 2165-S-1017 J-I4 8210 20 BF MO 3 B Act C 0 AI PIT 2YR n/a Emergency Exhaust Fan "A" STO Q n/a IAV-3 Filter Train Inlet Iso Vlv 2165-S-1017 J-11 8210 6 BF MO 3 B Act C 0 AI PIT 2YR n/a From RAB to Emergency STO Q n/a Exhaust Fan "A" IAV-4 Filter Train Inlet Iso Vlv 2165-S-1017 K-11 8210 20 BF MO 3 B Act C 0 AI PIT 2YR n/a From RAB to Emergency STO Q n/a Exhaust Fan "B" IAV-5 Inlet Iso Vlv From RAB to 2165-S-1017 K-14 8210 20 BF MO 3 B Act C 0 Al PIT 2YR n/a Emergency Exhaust Fan "B" STO Q n/a Revision 0 Page26 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table C T Valve Nomenclature Flow Diagram wg System Size; Actuator Safety" OM;Act/'orm Safety Fail Test Test CSJ/ROJ

' Bod Number Coord (inch) Class. Cat "Pass'os Pos Pos Type Freq RR I AV-6 Filter Train Inlet Iso Vlv 2165-S-1017 K-11 8210 BF MO 3 8 Act C 0 AI PIT 2YR n/a From RAB to Emergency STO Q n/a Exhaust Fan "8" IBD-I SG,"A" Tubesheet 2165-S-551 E-3 3010 2 GL AO 2 8 Act 0 C FSC Q n/a Blowdown Iso Vlv (Inbd) PIT 2YR n/a STC Q n/a IBD-11 SG "A" Blowdown Iso Vlv 2165-S-551 E-7 3010 4 GL AO 2 8 Act 0 C FSC Q n/a (CIV) PIT 2YR n/a STC Q n/a I BD-20 SG "8" Tubesheet 2165-S-551 J-3 3010 GL AO 2 8 Act 0 C FSC Q n/a Blowdown Iso Vlv (Inbd) PIT 2YR n/a STC Q n/a I BD-26 SG "8" Shell Blowdown Iso 2165-S-551 H-3 3010 4 GL AO 2 8 Act 0 C FSC Q n/a Vlv (Inbd) PIT 2YR n/a STC Q n/a I BD-30 SG "8" Blowdown Iso Vlv 2165-S-551 1-6 3010 4 GL AO 2 8 Act 0 C C FSC Q n/a (CIV) PIT 2YR n/a STC Q n/a I BD-39 SG "C" Tubesheet 2165-S-551 N-3 3010 GL AO 2 8 Act 0 C C FSC Q n/a Blowdown Iso Vlv (Inbd) PIT 2YR n/a STC Q n/a

. I BD-45 SG "C" Shell Blowdown Iso 2165-S-551 L-3 3010 4 GL AO 2 8 Act 0 C FSC Q n/a Vlv (Inbd) PIT 2YR n/a STC Q n/a I BD-49 SG "C" Blowdown Iso Vlv 2165-S-551 N-7 3010 4 GL AO 2 8 .Act 0 C FSC Q n/a (CIV) PIT 2YR n/a STC Q n/a I BD-7 SG "A" Shell Blowdown 2165-S-551 C-3 3010 4 GL AO 2 8 Act 0 C C FSC Q n/a Iso Vlv (Inbd) PIT 2YR n/a STC Q n/a Revision 0 Page27 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve T.

Flow Diagram Dwg System 'ize Body ~Actua

'Safety,', OM IAct /, Norm t Safety ~i Fail Test Test CSJ/ROJ Nomenclature

'at i

(inch) '

Number ,Coord,'-15

~,

Class ~ Pass Pos "

Pos Pos 'Type Freq RR II ICB-2 Train "A" Containment 2165-S-1017 8060 24 BF AO 2 A/C Act C 0/C C FSC Q n/a Vacuum Relief Vlv (CIV) LJ 2YR n/a PIT 2YR n/a SP 6MO n/a STC Q n/a STO Q n/a I CB-3 Train "A" Containment 2165-S-1017 G-16 8060 24 CK SA 2 A/C Act C 0/C n/a LJ 2YR n/a Vacuum Relief Vlv (CIV) SC RO CB-VRI SO RO CB-VRI SP RO CB-VRI 1CB-6 Train "B" Containment 2165-S-1017 H-15 8060 24 BF AO 2 A/C Act C 0/C C FSC Q n/a Vacuum Relief Vlv (CIV) LJ 2YR n/a PIT 2YR n/a SP 6MO n/a STC Q n/a STO Q n/a 1CB-7 Train "B" Containment 2165-S-1017 H-16 8060 24 CK SA 2 A/C Act C 0/C n/a LJ 2YR n/a Vacuum Relief Vlv (CIV) SC RO CB-VRl SO RO CB-VRl SP RO CB-VRI ICC-113 CCW Heat Exchanger "B" 2165-S-1319 G-16 4080 18 BF MO 3 B Act 0 0/C Al PIT 2YR n/a to Non-Essential Equipment STC Q n/a Iso Vlv STO Q n/a ICC-114 CCW Supply to Sample 2165-S-1319 G-18 4080 4 DA AO 3 B Act 0 C C FSC Q n/a Heat Exchangers PIT 2YR n/a STC Q n/a ICC-115 CCW Supply to Sample 2165-S-1319 G-18 4080 4 DA AO 3 B Act 0 C C FSC Q n/a Heat Exchangers PIT 2YR n/a STC Q n/a ICC-118 CCW Return from Sample 2165-S-1319 H-2 4080 4 CK SA 3 C Act 0/C C n/a SC Q n/a Heat Exchangers Revision 0 Page 28 of 145

0 HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table

[ Valve I Nomenclature ) Flow Diagram "g System Size iB d,A t t ~Safety OMIAeti]Norm1Safety! Fail Test Test CSJ/ROJ

(

Number a

Coord (inch)I .

I I Class CatIPass Pos, Pos Pos Type Freq RR 1CC-119 CCW Return from Sample 2165-S-1319 H-2 4080 4 CK SA 3 C Act 0/C C n/a SC Q n/a Heat Exchangers ICC-127 CCW Non-Essential Return 2165-S-1319 H-3 4080 18 BF MO 3 B Act 0 0/C AI PIT 2YR n/a to Header "B" STC Q n/a STO Q n/a 1CC-128 CCW Non-Essential Return 2165-S-1319 G-3 4080 18 BF MO 3 B Act 0 0/C AI PIT 2YR n/a to Header "A" STC Q n/a STO Q n/a 1CC-129 CCW Nonessential Return 2165-S-1319 G-4 4080 .75 RV SA 3 C Act C 0/C n/a SP IOYR n/a Relief Vlv ICC-147 CCW From RHR Heat 2165-S-1320 A-7 4080 12 GA MO 3 B Act C 0 AI PIT 2YR n/a Exchanger "A" Outlet Iso STO Q n/a Vlv.

ICC-167 CCW From RHR Heat 2165-S-1320 L-7 4080 12 GA MO 3 B Act C 0 Al PIT 2YR n/a Exchanger "B" Outlet Iso STO Q n/a Vlv.

1CC-176 CCW to Excess LTDN & 2165-S-1321 D-3 4080 6 GA MO 2 B Act 0 C AI PIT 2YR n/a RCDT Heat Exchangers STC Q n/a (CIV) 1CC-179 CCW to Excess LTDN & 2165-S-1321 D-3 4080 6 CK SA 2 C Act 0 0 n/a SO n/a RCDT Heat Exchangers ICC-186 CCW From RCDT Heat 2165-S-1321 D-8 4080 0.75 RV SA 2 C Act C 0/C n/a SP IOYR Exchanger Outlet Relief Vlv (CIV) 1CC-194 CCW From Excess LTDN 2165-S-1321 E-8 4080 3 RV SA 2 C Act C 0/C n/a SP IOYR n/a Heat Exchanger Outlet Relief Vlv (CIV) 1CC-202 CCW from Excess LTDN & 2165-S-1321 B-10 4080 6 GA MO 2 B Act 0 C AI PIT 2YR n/a RCDT Heat Exchangers STC Q n/a (CIV) 1CC-207 CCW Supply To RCPs lso 2165-S-1321 E- I 4080 6 GA MO 2 B Act 0 C AI PIT 2YR n/a Vlv STC RO CC-ROJ3 Revision 0 Page29 of 145

0 HNP-IST-002 HNP IST Program Plan -2nd Interval 5.3 Valve Table Valve Nomenclature Flow Diagram "g I System I Size,',

o y ,Actuatorj

~

T 7 tu I ISafetyIOMIAct/ Norm ISafetyII Fail

'est Test CSJ/ROJ Number >Coo rd~ ,

(inch),', ,l Class Cat Pass Pos, Pos Pos Type Freq RR ICC-208 CCW Supply To RCPs Iso 2165-S-1321 F-I 4080 6 GA MO 2 A Act 0 C AI LJ 2YR n/a Vlv - Outboard CIV PIT 2YR n/a STC RO CC-ROJ3 ICC-211 CCW Supply to RCPs- 2165-S-1321 F-I 4080 6 CK SA 2 A/C Act 0 0/C n/a LJ 2YR n/a Inboard CIV SC RO CC-ROJ I SO Q n/a ICC-216 CCW To RCP "A"Thermal 2165-S-1321 N-2 4080 CK SA 3 C Act 0 C n/a SDIS RO CC-VR2 Barrier Inlet Check Vlv I CC-219 CCW Return From RCP 2165-S-1321 N-4 4080 0.75 RV SA 3 C Act C 0/C n/a SP IOYR n/a "A"Thermal Barrier Relief ICC-227 CCW To RCP "B" Thermal 2165-S-1321 N-5 4080 2 CK SA 3 C Act 0 C n/a SDIS RO CC-VR2 Barrier Inlet Check Vlv I CC-230 CCW Return From RCP 2165-S-1321 N-8 4080 0.75 RV SA 3 C Act C 0/C n/a SP 10YR n/a "B" Thermal Barrier Relief ICC-238 CCW To RCP "C" Thermal 2165-S-1321 N-9 4080 2 CK SA 3 C Act 0 C n/a SDIS RO CC-VR2 Barrier Inlet Check Vlv ICC-241 CCW Return From RCP 2165-S-1321 N-11 4080 0.75 RV SA 3 C Act C 0/C n/a SP IOYR n/a "C" Thermal Barrier Relief ICC-249 CCW Return From RCP 2165-S-1321 E-15 4080 4 G'A MO 2 A Act 0 C AI LJ 2YR n/a Thermal Barriers - Inboard PIT 2YR n/a CIV STC RO CC-ROJ3 ICC-250 CCW Return From RCP 2165-S-1321 F-16 4080 0.75 CK SA 2 A/C Act C 0/C n/a LJ 2YR n/a Thermal Barriers - Inboard SC RO CC-ROJ I CIV SO RO CC-ROJ I ICC-251 CCW Return From RCP 2165-S-1321 E-15 4080 4 GA MO 2 A Act 0 C AI LJ 2YR n/a Thermal Barriers- PIT 2YR n/a Outboard CIV STC RO CC-ROJ3 ICC-252 CCW Return From RCPs 2165-S-1321 D-15 4080 4 GA MO 2 B Act 0 C AI PIT 2YR n/a Thermal Barrier Iso Vlv STC RO CC-ROJ3 ICC-294 CCW Return From RCP 2165-S-1321 F-12 4080 3 RV SA 3 C Act C 0/C n/a SP 10YR n/a Mtr. Brg. Coolers Relief Revision 0 Page30 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5,3 Valve Table Valve Number Nomenclature Q,Coord;,

) Flow Diagram )

"g System

~

'ody Actuator,

'(inch),

I t

yl,' OM LiAct Class Cat[~ Pass

~)

/ Norm Safety Pos Pos

~

Fail Pos

'est

~

. Test Type Freq

. CSJ/ROJ RR J (

ICC-297 CCW Return From RCP 2165-S-1321 E-12 4080 6 GA MO 2 A Act 0 C AI LJ 2YR n/a Mtr. Brg. Coolers - Inboard PIT 2YR n/a CIV STC RO CC-ROJ3 ICC-298 CCW Return From RCP 2165-S-1321 F-13 4080 0.75 CK SA 2 A/C Act C 0/C n/a LJ 2YR n/a Motor Bearing Coolers- SC RO CC-ROJ I Inboard CIV SO RO CC-ROJ I ICC-299 CCW Return From RCPs 2165-S-1321 E-12 4080 6 GA MO 2 A Act 0 C Al LJ 2YR n/a Iso Vlv - Outboard CIV PIT 2YR n/a STC RO CC-ROJ3 ICC-304 CCW To Gross Failed Fuel 2165 S 1322 A6 4080 075 DA AO 3 B Act 0 C C FSC Q n/a Detector PIT 2YR n/a STC Q n/a ICC-305 CCW To Gross Failed Fuel 2165-S-1322 B-6 4080 0.75 DA AO 3 B Act 0 C C FSC Q n/a Detector PIT 2YR n/a STC n/a I CC-306 CCW Return From Gross 2165-S-1322 C-6 4080 0.75 CK SA 3 C Act 0 C n/a SDIS RO CC-VR I Failed Fuel Detector I CC-307 CCW Return From Gross 2165-S-1322 C-6 4080 0.75 CK SA 3 C Act 0 C n/a SDIS RO CC-VR I Failed Fuel Detector ICC-313 CCW Outlet From Gross 2165-S-1322 E-5 4080 0.75 RV SA 3 C Act C 0/C n/a SP IOYR n/a Failed Fuel Detector Relief ICC-33 CCW Pump A Discharge 2165-S-1319 E-8 4080 18 CK SA 3 C Act 0/C 0/C n/a SC Q n/a Check Vlv SO Q n/a ICC-50 CCW Pump "B" Discharge 2165-S-1319 K-8 4080 18 CK SA 3 C Act 0/C 0/C n/a SC Q n/a Check Vlv SO Q n/a ICC-556 RHR Htx "A" Press Relief 2165-S-1320 B-7 4080 I CK SA 3 C Act 0/C 0 n/a SO RO CC-ROJ2 Bypass Line Check Vlv ICC-558 RHR Htx "B" Press Relief 2165-S-1320 M-7 4080 I CK SA 3 C Act 0/C 0 n/a SO RO CC-ROJ2 Bypass Line Check Vlv Revision 0 Page31 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table T

Valve Nomenclature Flow Diagram g i System Size Body",Actuat SafetylOMIAct/ Norm >Safety Fail Test Test CSJ/ROJ Number t ,Coord,',  ; (inch);

Class i Cat Pass t ",, Pos ,', Pos Pos .Type Freq RR i = . l j I ICC-561 Fuel Pool Heat Exchangers 2165-S-1322 SO I J-5 4080 I CK SA 3 C Act 0 0 n/a SO RO CC-ROJ2 I & 4B Press. Relief Bypass Line Check ICC-563 Seal Water Hx Shell Side 2165-S-1322 J-2 4080 .75 CK'A 3 C Act 0 0 n/a SO RO CC-ROJ2 Thermal Relief ICC-565 Letdown Hx Shell Side 2165-S-1322 J-4 4080 .75 CK SA 3 C Act 0 0 n/a SO RO CC-ROJ2 Thermal Relief ICC-567 Vent Condenser Thermal 2165-S-1322 K-7 4080 .75 CK SA 3 C Act 0 0 n/a SO RO CC-ROJ2 Relief I CC-569 Recycle Evaporator 2165-S-1322 K-11 4080 .75 CK SA 3 C Act 0 0 n/a SO RO CC-ROJ2 Condenser Thermal Relief ICC-571 Distillate Cooler Thermal 2165-S-1322 K-9 4080 .75 CK SA 3 C Act 0 0 n/a SO RO CC-ROJ2 Relief ICC-573 Fuel Pool Heat Exchangers 2165-S-1322 SOI 13 4080 I CK SA 3 C Act 0 0 n/a SO RO CC ROJ2 I & 4A Press. Relief Bypass Line Check I CC-64 CCW Pump C Discharge 2165 S 1319 H 8 4080 18 CK SA 3 C Act 0/C 0/C n/a SC Q n/a Check Vlv SO Q n/a ICC-99 CCW Heat Exchanger "A" 2165-S-1319 F-16 4080 18 BF MO 3 B Act 0 0/C AI PIT 2YR n/a to Non-Essential Equipment STC Q n/a Iso Vlv STO Q n/a ICE-1157 MDAFWP "A" Inlet Relief 2165-S-545 1-7 3070 IXI RV SA 3 C Act C 0/C n/a SP IOYR n/a Vlv ICE-1158 MDAFWP "B" Inlet Relief 2165-S-545 1-8 3070 IXI RV SA 3 C Act C 0/C n/a SP I OYR n/a Vlv ICE-1159 TDAFWP Inlet Relief Vlv 2165-S-545 I 9 3070 I XI RV SA 3 C Act C 0/C SP IOYR n/a ICE-36 CST to MDAFWP "A" Inlet 2165-S-545 H7 3070 6 CK SA 3 C Act C 0/C PSO Q CE-CSJ I Check Vlv SDIS RO CE-VR I SO CS CE-CSJ I Revision 0 Page 32 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval

'.3 Valve Table

'wg Size I

Actuator'Safety OM'Act/t No"m I Safety, Fail Test- Test CSJ/ROJ Number I

Nomenclature Flow Diagram

'Coo rd S tern (inch)

Bod Class; Cat 'Pass Pos 'os Pos Type Freq RR ICE-46 CST to MDAFWP "8" Inlet 2165-S-545 H-8 3070 6 CK SA 3 C Act C 0/C n/a PSO Q CE-CSJ I Check Vlv SDIS RO CE-VR I SO CS CE-CSJ I 1CE-56 CST to TDAFWP Inlet 2165-S-545 H-9 3070 8 CK SA 3 C Act C 0/C n/a PSO Q CE-CSJ I Check Vlv SDIS RO CE-VR I SO CS CE-CSJ I ICH-10 Chilled Water Pump "IA" 2165-S-998 S02 1-4 4085 I RV SA 3 C Act C 0/C n/a SP I OYR n/a Suction Relief Vlv 1CH-115 AH-30 and AH-63 (z) 2165-S-998 H-14 4085 4 BF AO 3 8 Act 0 C FSC Q n/a Chilled Water Train "A" PIT 2YR n/a Supply Iso Vlv STC Q n/a 1CH-116 AH-30 and AH-63 (z) 2165-S-998 H-14 4085 4 BF AO 3 . 8 Act 0 C FSC Q n/a Chilled Water Train "A" PIT 2YR n/a Supply Iso Vlv STC Q n/a ICH-125 AH-30 and AH-63 (z) 2165-S-998 L 10 4085 4 BF AO 3 8 Act 0 G FSC Q n/a Chilled Water Train "A" PIT 2YR n/a Return Iso Vlv STC Q n/a ICH-126 AH-30 and AH-63 (z) 2 I 65-S-998 L-IO 4085 4 BF AO 3 8 Act 0 C FSC Q n/a Chilled Water Train "A" PIT 2YR n/a Return Iso Vlv STC Q n/a 1CH-1397 Demin Makeup to Train 2165-S-998 S02 J-4 4085 I GL SO 3 8 Act 0 C FSC Q n/a "A" Chilled Water Iso Vlv PIT 2YR n/a STC Q n/a 1CH-1398 Demin Makeup to Train 2165-S-998 S02 J-4 4085 I GL SO 3 8 Act 0 C FSC Q n/a "A" Chilled Water Iso Vlv PIT 2YR n/a STC Q n/a 1CH-1399 Demin Makeup to Train 2165-S-999 S02 J-4 4085 I GL SO 3 8 Act 0 C C FSC Q n/a "8" Chilled Water Iso Vlv PIT 2YR n/a STC Q n/a STO Q n/a Revision 0 Page33 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve Nomenclature Flow Diagram, wg System Size 'B d A t Safety OM;Act/ Norm,'Safety', Fail Test Test CSJ/ROJ Number ',Coo rd (inch) Class Cat Pass Pos Pos Pos Type Freq RR I CH-1400 Demin Makeup to Train 2165-S-999 S02 J-4 4085 I GL SO 3 B Act 0 C C FSC Q n/a "B" Chilled Water Iso Vlv PIT 2YR n/a STC Q n/a I CH-148 AH-30 and AH-63 (z) 2165-S-999 A-16 4085 4 BF AO 3 B Act 0 C C FSC Q n/a Chilled Water Train "B" PIT 2YR n/a Supply Iso Vlv STC Q n/a ICH-149 AH-30 and AH-63 (z) 2165-S-999 A-16 4085 4 BF AO 3 B Act 0 C C FSC Q n/a Chilled Water Train "B" PIT 2YR n/a Supply Iso Vlv STC Q n/a ICH-19 Chilled Water Pump "IA" 2165-S-998 S02 H-8 4085 0.75 RV SA 3 C Act C 0/C n/a SP IOYR n/a Discharge Relief Vlv ICH-196 AH-30 and AH-63 (z) 2165-S-999 L-15 4085 4 BF AO 3 B Act 0 C FSC Q n/a Chilled Water Train "B" PIT 2YR n/a Return Iso Vlv STC Q n/a ICH-197 AH-30 and AH-63 (z) 2165-S-999 L-15 4085 4 BF AO 3 B Act 0 C FSC Q n/a Chilled Water Train "B" PIT 2YR n/a Return Iso Vlv STC Q n/a ICH-199 AH-5 (I A-SA) Temperature 2165-S-998 S03 B-1 4085 2.5 3W AO 3 B Act 0/C 0 0 FSO Q n/a Control Iso Vlv. STO Q n/a I CH-213 AH-6 (I A-SA) Temperature 2165-S-998 S03 B-5 4085 3 3W AO 3 B Act 0/C 0 0 FSO Q n/a Control Iso Vlv. STO Q n/a ICH-232 AH-7 (I A-SA) Temperature 2165-S-998 S03 B-8 4085 3 3W AO 3 B Act 0/C 0 0 FSO Q n/a Control lso Vlv. STO Q n/a ICH-251 AH-9 (1A-SA) Temperature 2165-S-998 S03 B-12 4085 2.5 3W AO 3 B Act 0/C 0 0 FSO Q n/a Control Iso Vlv. STO Q n/a ICH-265 AH-10 (I A-SA) 2165-S-998 S03 B-15 4085 2.5 3W AO . 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

ICH-279 AH-12 (IA-SA/IB-SB) 2165-S-998 S03 F-5 4085 4 3W AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

Revision 0 Page34 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table I

Valve System.I Size IBody IActuator!Safet)OM Act/I Norm "Safety Fail Test Test CSJ/ROJ Nomenclature Flow Diagram

'os Number <Coo rd>! I, (inch) .

Ciassi Cat Pass ~ Pos Pos -

Type Freq RR ICH-323 AH-15 (I A-SA) 2165-S-998 S03 F-15 4085 2.5 3W EH 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

I CH-34 Chiller "A" Chilled Water 2165-S-998 S02 F-11 4085 0.75 RV SA 3 C Act C 0/C n/a SP IOYR n/a Outlet Header Relief Vlv ICH-343 AH-16 (I A-SA) 2165-S-998 S03 K-I 4085 3 3W AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

I CH-363 AH-17 (I -4A-SA) 2165-S-998 S03 K-5 4085 2.5 3W AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

ICH-381 AH-19 (I A-SA) 2165-S-998 S03 K-8 4085 2.5 3W AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

ICH-394 AH-20 (I A-SA) 2165-S-998 S03 K-12 4085 2.5 3W AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a.

Vlv.

ICH-409 AH-23 (I X-SA) 2165-S-998 S04 B-l 4085 I GL AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

ICH-422 AH-24 (I X-SA) 2165-S-998 S04 B-5 4085 1.5 GL AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

ICH-434 AH-26 (I A-SA) 2165-S-998 S04 B-8 4085 1.5 GL AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

I CH-446 AH-28 (I A-SA) 2165-S-998 S04 B-12 4085 2.5 3W AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

ICH-460 AH-92 (I A-SA) 2165-S-998 S04 G-8 4085 1.5 3W AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

Revision 0 Page35 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve Flow Diagram, "g System Actuator Safety OM Act / Norm Safety Fail Test Test CSJ/ROJ Number Nomenclature

,~Coo rd"

'inch)" Body Class 'at. Pass

- ~ I, Pos Pos Pos Type Freq RR ICH-472 AH-93 (I X-SA) 2165-S-998 S04 G-12 4085 1.5 3W AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

ICH-485 AH-11 (IA-SA) 2165-S-998 S03 G- I 4085 2.5 GL AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

ICH-50 Expansion Tank "IB" 2165-S-999 S02 G-4 4085 I RV SA 3 C Act C 0/C n/a SP IOYR n/a Relief Vlv I CH-54 Chilled Water Pump "IB" 2165-S-999 S02 1-5 4085 I RV SA 3 C Act C 0/C n/a SP IOYR n/a Suction Relief Vlv I CH-551 AH-5 (I B-SB) Temperature 2165-S-999 S03 B- I 4085 2.5 3W AO 3 B Act 0/C 0 0 FSO Q n/a Control Iso Vlv. STO Q n/a ICH-564 AH-6 (I B-SB) Temperature 2165-S-999 S03 B-5 4085 3 3W AO 3 B Act 0/C 0 0 FSO Q n/a Control Iso Vlv. STO Q n/a ICH-583 AH-7 (I B-SB) Temperature 2165-S-999 S03 B-8 4085 3 3W AO 3 B Act 0/C 0 0 FSO Q n/a Control Iso Vlv. STO Q n/a ICH-6 Expansion Tank "IA" 2165-S-998 S02 G-4 4085 RV SA 3 C Act C 0/C n/a SP IOYR n/a Relief Vlv ICH-603 AH-8 (I X-SB) Temperature 2165-S-999 S03 B-13 4085 2.5 GL AO 3 B Act 0/C 0 0 FSO Q n/a Control Iso Vlv. STO Q n/a ICH-616 AH-9 (I B-SB) Temperature 2165-S-999 S03 F-5 4085 2.5 3W AO 3 B Act 0/C 0 0 FSO Q n/a Control Iso Vlv. STO Q n/a ICH-63 Chilled Water Pump "I B" 2165-S-999 S02 H-8 4085 0.75 RV SA 3 C Act C 0/C n/a SP IOYR n/a Discharge Relief Vlv ICH-630 AH-IO (I B-SB) 2165-S-999 S03 F-8 4085 2.5 3W AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

ICH-643 AH-11 (I B-SB) 2165-S-999 S03 K- I 4085 2.5 GL AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

Revision 0 Page36 of 145

N HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table

~ =-

Valve Nomenclature Flow Diagram g System Body ~Safety)OM Act/ Norm Safety Fail Test Test, CSJ/ROJ

)

Number >Coord (inch) ) Class~i Cat Pass Pos Pos ll Pos iType. Freq, RR ICH-680 AH-13 (I A-SB/I B-SB) 2165-S-999 S03 K-9 4085 4 3W AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

ICH-703 AH-15 (I B-SB) 2165-S-999 S03 F-13 4085 2.5 3W EH 3 B Act 0/C 0 0 FSO Q n/a Temperature Control lso STO Q n/a Vlv.

ICH-726 AH-16 (I B-SB) 2165-S-999 S04 B- I 4085 3 3W AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

ICH-745 AH-17 (I-4B-SB) 2165-S-999 S04 B-6 4085 2.5 3W AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

ICH-764 AH-19 (I B-SB) 2165-S-999 S04 B-9 4085 2.5 3W AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

ICH-777 AH-20 (I B-SB) 2165-S-999 S04 B-13 4085 2.5 3W AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

ICH-78 Chiller "B" Chilled Water 2165-S-999 S02 G-12 4085 0.75 RV SA 3 C Act C 0/C n/a SP IOYR n/a Outlet Header Relief Vlv ICH-793 AH-25 (I X-SB) 2165-S-999 S04 G-7 4085 1.5 GL AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

I CH-807 AH-26 (I B-SB) 2165-S-999 S04 K- I 4085 1.5 GL AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

ICH-820 AH-28 (I B-SB) 2165-S-999 S04 K-5 4085 2.5 3W AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

ICH-833 AH-29 (I X-SB) 2165-S-999 S04 K-9 4085 I GL AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

Revision 0 Page 37 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Number Nomenclature Flow Diagram )

wg System Coord

'ody Actuator (inch) =

Act/ Norm Class Cat Pass Pos Safety Pos Fail Pos Test Test I Type Freq',

CSJ/ROJ,'R 1CH-846 AH-92 (I B-SB) 2165-S-999 S04 K-13 4085 1.5 3W AO 3 B Act 0/C 0 0 FSO Q n/a Temperature Control Iso STO Q n/a Vlv.

ICM-2 Hydrogen Purge Exhaust 2165-S-1017 C-16 2075 3 - BF AO 2 A Pass LC C C LJ 2YR n/a Iso (CIV) PIT 2YR n/a ICM-4 Hydrogen Purge Exhaust . 2165-S-1017 C-14 2075 3 BF MAN 2 A Pass LC C n/a LJ 2YR n/a Iso (CIV)

ICM-5 Hydrogen Purge Makeup 2165-S-1017 1-14 2075 3 BF MAN 2 A Pass LC C n/a LJ 2YR n/a Iso (CIV)

ICM-7 Hydrogen Purge Makeup 2165-S-1017 1-16 2075 3 CK SA 2 A/C Act C C n/a LJ 2YR n/a Iso (CIV)

I CP-I Containment Pre-Entry 2165-S-1017 E-15 8170 42 BF AO 2 A Act LC C C FSC CS CP-CSJ I Purge Exhaust Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC CS CP-CSJ I I CP-10 Containment Pre-Entry 2165-S-1017 '-16 8170 42 BF AO 2 A Act LC C C FSC CS CP-CSJ I Purge Makeup Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC CS CP-CSJ I 1CP-3 Normal Containment Purge 2165-S-1017 F-15 8170 8 BF AO, 2 A Act 0/C C C FSC Q n/a Exhaust Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a I CP-4 Containment Pre-Entry 2165-S-1017 E-16 8170 42 BF AO 2 A Act LC C C FSC CS CP-CSJ I Purge Exhaust Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC CS CP-CSJ I ICP-5 Normal Containment Purge 2165-S-1017 F-16 8170 8 BF AO 2 A Act 0/C C C FSC Q n/a Exhaust Vlv (CIV) Ll '2YR n/a PIT 2YR n/a STC Q n/a Revision 0 Page 38 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve Nomenclature I Flow Diagram Norm,', Safety ',"

Fail -

Test Test CSJ/ROJ Number Coordt '(inch) ~ i - Class" ,Cat Pass Pos t Pos j Pos ~Type Freq RR J lt it I ~

.I ICP-6 Normal Containment Purge 2165-S-1017 F-15 8170 8 BF AO 2 A Act 0/C C C FSC Q n/a Makeup Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC n/a ICP-7 Containment Pre-Entry 2165-S-1017 G-15 8170 42 BF AO 2 A Act LC C C FSC CS CP-CSJ I Purge Makeup Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC CS CP-CSJ I I CP-9 Normal Containment Purge 2165-S-1017 F-16 8170 8 BF AO 2 A Act 0/C C C FSC Q n/a Makeup Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a ICS-I RCS Letdown Line Iso Vlv 2165-S-1303 A-3 2060 3 GL AO I B Act 0 C C FSC CS CS-CSJ I PIT 2YR n/a STC CS CS-CSJ I I CS-10 Letdown Line Relief Vlv 2165-S-1303 A-11 2060 2 RV SA . 2 A/C Act C 0/C n/a LJ 2YR n/a (CIV) SP IOYR n/a I CS-11 Letdown Iso (CIV) 2165-S-1303 A-17 2060 3 GL AO 2 A Act 0 C C FSC CS CS-CSJI LJ 2YR n/a PIT 2YR n/a STC CS CS-CSJ I ICS-165 VCT Outlet Iso - LCV-115C 2165-S-1305 G-11 2060 4 GA MO 2 B Act 0 C Al PIT 2YR n/a STC CS CS-CSJ3 ICS-166 VCT Outlet Iso - LCV-115E 2165-S-1305 G-11 2060 4 GA MO 2 B Act 0 C Al PIT 2YR n/a STC CS CS-CSJ3 ICS-167 VCT Outlet Check Vlv 2165-S-1305 G-11 2060 4 CK SA 2 A/C Act 0 C n/a LK 2YR n/a SC CS CS-CSJS ICS-168 CSIP Suction Header Cross 2165-S-1305 1-11 2060 S GA MO 2 B Pass 0 0 Al PIT 2YR n/a Connect ICS-169 CSIP Suction Header Cross 2165-S-1305 J- I I 2060 8 GA MO 2 B Pass 0 0 AI PIT 2YR n/a Connect Revision 0 Page39 of 145

J HNP-IST-002 HNP IST Program Plan -2nd Interval 5.3 Valve Table Valve Flow Diagra, Dwg Syste Size 'Body IActu t,Safety',OM Act/t Norm ISafety Fail Test 'est CSJ/ROJ Number Nomenclature Coord (inch)

Jl Class Cat 'ass I

'os t Pos Pos Type Freq RR ICS-170 CSIP Suction Header Cross 2165-S-1305 I-ll 2060 8 GA MO 2 B Pass 0 0 Al PIT 2YR n/a Connect ICS-171 CSIP Suction Header Cross 2165-S-1305 K-11 2060 8 GA MO 2 B Pass 0 0 AI PIT 2YR n/a Connect ICS-178 CSIP "IA"Discharge 2165-S-1305 H-7 2060 3 CK SA 2 C Act 0/C 0/C n/a PSO Q CS-ROJ7 Check Vlv SC Q n/a SO RO CS-ROJ2 I CS-179 CSIP "IA" Minimum Flow 2165-S-1305 H-8 2060 2 CK SA 2 C Act 0/C 0/C n/a SC Q n/a Recirculation Check Vlv SO Q n/a ICS-182 CSIP "IA"Minimum Flow 2165-S-1305 G-7 2060 2 GL MO 2 B Act 0 C Al PIT 2YR n/a Line Iso Vlv STC Q n/a ICS-192 CSIP "IB" Discharge 2165-S-1305 K-7 2060 3 CK SA 2 C Act 0/C 0/C n/a PSO Q CS-ROJ2 Check Vlv SC Q n/a SO RO CS-ROJ2 I CS-193 CSIP "I B" Minimum Flow 2165-S-1305 K-8 2060 2 CK SA 2 C Act 0/C 0/C n/a SC Q n/a Recirculation Check Vlv SO Q n/a ICS-196 CSIP "IB" Minimum Flow 2165-S-1305 J-7 2060 2 GL MO 2 B Act 0 C AI PIT 2YR n/a Line Iso Vlv STC Q n/a ICS-2 RCS Letdown Line Iso Vlv 2165-S-1303 A-3 2060 3 GL AO I B Act 0 C C FSC CS CS-CSJ I PIT 2YR n/a STC CS CS-CSJ I I CS-206 CSIP "IC" Discharge 2165-S-1305 J-7 2060 3 CK SA 2 C Act 0/C 0/C n/a PSO Q CS-ROJ2 Check Vlv SC Q n/a SO RO CS-ROJ2 ICS-207 CSIP "IC" Minimum Flow 2165-S-1305 1-8 2060 2 CK SA 2 C Act 0/C 0/C n/a SC Q n/a Recirculation Check Vlv SO Q n/a ICS-210 CSIP "IC" Minimum Flow 2165-S-1305 1-7 2060 2 GL MO 2 B Act 0 C Al PIT 2YR n/a Line Iso Vlv STC Q n/a F-ICS-214 CSIP Minimum Flow Iso 2165-S-1305 .G-4 2060 3 GA MO 2 B Act 0 C AI PIT 2YR n/a Vlv STC Q n/a Revision 0 Page 40 of 145

HNP-IST-002 HNP IST Program Plan -2nd Interval 5.3 Valve Table Valve Flow Dia ram Dvvg Size Body Actuator Safety OM Act/ Norm "Safety Fall Test Test CSJ/ROJ Nomenclature System Number Coord (inch) Class Cat Pass Pos Pos,'os ,

Type Freq RR I CS-217 CSIP Discharge Header 2165-S-1305 1-6 2060 4 GA MO 2 B Act 0 0/C Al PIT 2YR n/a Cross Connect STC Q n/a ICS-218 CSIP Discharge Header 2165-5-1305 J-6 2060 4 GA MO 2 B Act 0 0/C Al PIT 2YR n/a Cross Connect STC Q n/a ICS-219 CSIP Discharge Header 2165-S-1305 1-6 2060 4 GA MO 2 B Act 0 0/C AI PIT 2YR n/a Cross Connect STC Q n/a ICS-220 CSIP Discharge Header 2165-S-1305 K-6 2060 4 GA MO 2 B Act 0 0/C AI PIT 2YR n/a Cross Connect STC Q n/a ICS-231 Charging Flow Control Vlv 2165-S-1305 H-4 2060 3 GL AO 2 B Act T 0 O FSO CS CS-CSJ2 STO CS CS-CSJ2 I CS-235 Charging Line Iso Vlv 2165-S-1305 H-2 2060 3 GA MO 2 B Act 0 0/C AI PIT 2YR n/a STC CS CS-CSJ2 1CS-238 Charging Line Iso Vlv- 2165-S-1303 B-17 2060 3 GA MO 2 A Act 0 0/C AI LJ 2YR n/a CIV (otbd) PIT 2YR n/a STC CS CS-CSJ I ICS-278 BAT Pumps to CSIP 2165-S-1305 J-16 2060 2 GL MO 2 B Act C 0 Al PIT 2YR n/a Common Supply Header STO Q n/a Iso Vlv ICS-279 BAT Pumps to CSIP 2165-S-1305 J-17 2060 2 CK SA 2 C Act C 0 n/a SO CS CS-CSJ4 Supply Check Vlv ICS-283 Boric Acid Makeup to the 2165-S-1305 J-14 2060 2 GL AO 2 B Act 0/C C 0 FSO Q n/a VCT Flow Control Vlv PIT 2YR n/a FCV-113A STC Q n/a I CS-290 RHRS "A" HX to CSIP 2165-S-1305 J-12 2060 .75X I RV SA 2 C Act C 0/C SP IOYR n/a Suction Relief Vlv ICS-291 CSIP Suction from RWST 2165-S-1305 1-12 2060 8 GA MO 2 B Act C 0/C Al PIT 2YR n/a Iso Vlv - LCV-115B STC CS CS-CSJ3 STO CS CS-CSJ3 ICS-292 CSIP Suction from RWST 2165-S-1305 K-12 2060 8 GA MO 2 B Act C 0/C AI PIT 2YR n/a Iso Vlv - LCV-115D STC CS CS-CSJ3 STO CS CS-CSJ3 Revision 0 Page41 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve Number Nomenclature Fl D Dlvg $

,Coord I

Size (inch)

B d A I I, ClassCat Safety! OM Act /'orm I

Pass Pos Safety

'os I Fail Pos

, Test Test Type Freq CSJ/ROJ RR I CS-293 RHRS "B" HX to CSIP 2165-S-1305 K-13 2060 .75X I RV SA 2 C Act C 0/C n/a SP IOYR n/a Suction Relief Vlv I CS-294 RWST to CSIP Suction 2165-S-1305 K-14 2060 8 CK SA 2 C Act C 0/C n/a PSO CS CS-ROJ3 Supply Check Vlv SC CS CS-CSJS SO RO CS-ROJ3 ICS-310 RCP Seal Water Return 2165-S-1305 E-4 2060 75X I RV SA 2 C Act C 0/C n/a SP IOYR n/a Relief Vlv ICS-341 RCP "A" Seal Water 2165-S-1303 K-3 2060 1.5 GL MO 2 A Act 0 0/C AI U 2YR n/a Injection Iso Vlv (CIV) PIT 2YR n/a STC RO CS-ROJ4 ICS-344 RCP "A" Seal Water 2165-S-1303 K-3 2060 1.5 CK SA 2 A/C Act 0 0/C n/a LJ 2YR n/a Injection Check Vlv (CIV) SC RO CS-ROJ I SO Q n/a I CS-348 RCP "A" Seal Water 2165-S-1303 - J-3 2060 1.5 CK SA I C Act 0 0/C n/a SC RO CS-ROJ5 Injection Check SO Q n/a ICS-349 RCP "A" Seal Water 2165-S-1303 1-3 2060 1.5 CK SA I C Act 0 0/C n/a SC RO CS-ROJ5 Injection Check SO Q n/a I CS-382 RCP "B" Seal Water 2165-S-1303 SO I L-3 2060 1.5 GL MO 2 A Act 0 0/C AI LJ 2YR n/a Injection Iso Vlv (CIV) PIT 2YR n/a STC RO CS-ROJ4 ICS-385 RCP "B" Seal Water 2165-S-1303 SO I K-3 2060 1.5 CK SA 2 A/C Act 0 0/C n/a U 2YR n/a Injection Check Vlv (CIV) SC RO CS-ROJ I SO Q n/a ICS-389 RCP "B" Seal Water 2165-S-1303 SO I J-3 2060 I.S CK SA I C Act 0 0/C n/a SC RO CS-ROJS Injection Check SO Q n/a ICS-390 RCP "B" Seal Water 2165-S-1303 SO I 1-3 2060 1.5 CK SA I C Act 0 0/C n/a SC RO CS-ROJS Injection Check SO Q n/a ICS-423 RCP "C" Seal Water 2165-S-1303 S02 K-3 2060 1.5 GL MO 2 A Act 0 0/C Al LJ 2YR n/a Injection Iso Vlv (CIV) PIT 2YR n/a STC RO CS-ROJ4 Revision 0 Page42 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve Dwg S stem Size Body Actuat

'I 7

)Safety'OM Act/, Norm ISafety+ Fail 'est Test CSJ/ROJ Nomenclature Flow Diagr

'at Type 'req I

'Coord Number (inch) ~

I Class Pass I Pos Pos Pos RR I,. i I ICS-426 RCP "C" Seal Water 2165-S-1303 S02 K-3 2060 1.5 CK SA 2 A/C Act 0 0/C n/a LJ 2YR n/a Injection Check Vlv (CIV) SC RO CS-ROJ I SO Q n/a ICS-430 RCP "C" Seal Water 2165-S-1303 S02 J-3 2060 1.5 CK SA I C Act 0 0/C n/a SC RO CS-ROJ5 Injection Check SO Q n/a ICS-431 RCP "C" Seal Water 2165-S-1303 S02 1-3 2060 1.5 CK SA I C Act 0 0/C n/a SC RO CS-ROJ5 Injection Check SO n/a ICS-460 RCS Excess Letdown 2165-S-1303 D-8 2060 I GL AO I B Act C C C FSC Q n/a Upstream Iso Vlv PIT 2YR n/a STC Q n/a I CS-461 RCS Excess Letdown 2165-S-1303 D-8 2060 I GL AO I B Act C C C FSC Q n/a Downstream Iso Vlv PIT 2YR n/a STC Q n/a ICS-467 RCP Seal Water Return & 2165-S-1303 D-16 2060 2 RV SA 2 C Act C 0/C n/a SP IOYR n/a Excess LTDN Line Relief Vlv ICS-470 RCP Seal Water Return & 2165-S-1303 D-16 2060 2 GL MO 2 A Act 0 C Al LJ 2YR n/a Excess LTDN (CIV) PIT 2YR n/a STC RO CS-ROJ4 1CS-471 RCP Seal Water Return & 2165-S-1303 E-16 2060 0.75 CK SA 2 A/C Act C 0/C n/a LJ 2YR n/a Excess Letdown Thermal SC RO CS-ROJ I Relief Check (CIV) SO RO CS-ROJ I I CS-472 RCP Seal Water Return & 2165-S-1303 D-17 2060 2 GL MO 2 A Act 0 C Al LJ 2YR n/a Excess LTDN (CIV) PIT 2YR n/a STC RO CS-ROJ4 I CS-477 CVCS Normal Charging 2165-S-1303 B-16 2060 3 CK SA 2 A/C Act 0 0/C n/a LJ 2YR n/a Line Check Vlv (CIV) SC RO CS-ROJ I SO Q n/a ICS-480 Alternate Charging Line Iso 2165-S-1303 BP 2060 3 GL AO 2 B Act C 0/C 0 FSO CS CS-CSJ7 Vlv PIT 2YR n/a STO CS CS-CSJ7 Revision 0 Page43 of 145

HNP-IST-002 HNP IST Program Plan -2nd Interval 5.3 Valve Table t

Valve Number ICS-483 Nomenclature RCS Alternate Charging I

Flow Diagram 2165-S-1303 TDvg B-3 System 2060 Size (inch) 3 I",'.

IB CK d IA I J

SA I

j I

7

'~Safety',OM!Act/I Norm ISafety Class,'at C

'Pass Act l Pos C

I Pos 0/C

~ Fail Pos n/a Test Test Type Frcq SC RO CSJ/ROJ RR CS-ROJ8 Line Check Vlv SO CS CS-CSJ7 ICS-486 RCS Alternate Charging 2165-S-1303 B-3 2060 CK SA I C Act C 0/C n/a SC RO CS-ROJ8 Line Check Vlv SO CS CS-CSJ7 ICS-487 Pressurizer Auxiliary Spray 2165-S-1303 D-4 2060 GL AO 2 B Pass C C PIT 2YR n/a Vlv ICS-488 Pressurizer Auxiliary Spray 2165-S-1303 C-3 2060 3 CK SA I C Act C C n/a SC RO CS-ROJ8 Line Injection Check Vlv I CS-491 Pressurizer Auxiliary Spray 2165-S-1303 C-3 2060 3 CK SA I C Act C C n/a SC RO CS-ROJ8 Line Injection Check Vlv I CS-492 Normal Charging Line Iso 2165-S-1303 C-4 2060 3 GL AO 2 B Act 0 0/C 0 FSO CS CS-CSJ7 Vlv PIT 2YR n/a STC CS CS-CSJ7 ICS-493 RCS Normal Charging 2165-S-1303 C-4 2060 .75 CK SA 2 C Act 0 0 n/a SO RO CS-ROJ6 Isolation Valve Bypass ICS-497 RCS Normal Charging Line 2165-S-1303 C-3 2060 CK SA I C Act 0 0/C n/a SC RO CS-ROJ8 Check Vlv SO Q n/a I CS-500 RCS Normal Charging Line 2165-S-1303 B-3 2060 3 CK SA I C Act 0 0/C n/a SC RO CS-ROJ8 Check Vlv SO Q n/a ICS-525 Boric Acid Gravity Feed 2165-S-1307 E-7 2060 3 CK SA 3 C Act C 0 n/a SO RO CS-ROJ7 Line Check Vlv ICS-526 Boric Acid Gravity Feed 2165-S-1307 E-10 2060 DA MAN 2 B Act C 0/C n/a SC RO CS-ROJ7 Line Manual Isolation Vlv SO RO CS-ROJ7 I CS-536 Boric Acid Transfer Pump 2165-S-1307 E-7 2060 2 CK SA 3 C Act C 0/C n/a SC Q n/a "A" Discharge Check Vlv SO Q n/a ICS-546 Boric Acid Transfer Pump 2165-S-1307 G-7 2060 2 CK SA 3 C Act C 0/C n/a SC Q n/a "B" Discharge Check Vlv SO n/a Q

ICS-559 Boric Acid Filter Inlet Iso 2165-S-1307 E-3 2060 2 PL AO 3 B Pass 0 0 0 PIT 2YR n/a Vlv Revision 0 Page44 of 145

HNP-IST-002 HNP IST Program Plan -2nd Interval 5.3 Valve Table f

Valve wg System Norm Safety', Fail Test Test CSJ/ROJ l(inch) ',,"Class Nomenclature Flow Diagram ',,

Number ',Coo rd', Cat Pass '

Pos i Pos Pos 'Type Freq RR I j I I CS-562 Boric Acid Filter Backwash 2165-S-1307 D-3 2060 PL AO 3 B Pass C C C PIT 2YR n/a Iso Vlv ICS-563 Boric Acid Filter Outlet lso 2165-S-1307 E-2 2060 2 PL AO B Pass 0 0 0 PIT 2YR n/a Vlv ICS-7 Letdown Orifice Iso Vlv- 2165-S-1303 B-10 2060 GL AO 2 A Act 0/C C FSC Q n/a Orifice "A"45 GPM (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a ICS-745 CSIP Alternate Minimum 2165-S-1304 H-16 2060 2 GL MO B Act 0 0/C AI PIT 2YR n/a Flow Line Iso Vlv STC Q n/a I CS-746 CSIP Alternate Minimum 2165-S-1304 H-17 2060 2 GL MO 2 B Act C 0/C AI PIT 2YR n/a Flow Line Iso Vlv STC Q n/a STO Q n/a I CS-752 CSIP Alternate Minimum 2165-S-1304 J-16 2060 2 GL MO B Act C 0/C AI PIT 2YR n/a Flow Line Iso Vlv STC Q n/a STO Q n/a ICS-753 CSIP Alternate Minimum 2165-S-1304 J-16 2060 2 GL MO 2 B Act 0 0/C AI PIT 2YR n/a Flow Line Iso Vlv STC Q n/a ICS-774 RCS Normal Charging 2165-S-1303 C-5 2060 .75 CK SA C Act 0 0 SO RO CS-ROJ6 Isolation Valve Bypass k

ICS-775 CSIP Supply Check Vlv 2165-S-1305 J-13 2060 8 CK SA C Act C 0/C SC CS CS-CSJ6 From The RHR IB Heat SO CS CS-CSJ6 Exchanger ICS-776 CSIP Supply Check Vlv 2165-S-1305 K-13 2060 8 CK SA 2 C Act C 0/C n/a SC CS CS-CSJ6 From The RHR IA Heat SO CS CS-CSJ6 Exchanger ICS-8 Letdown Orifice Iso Vlv- 2165-S-1303 B-11 2060 2 GL AO 2 A Act 0/C C FSC Q n/a Orifice "B" 60 GPM (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a Revision 0 Page 45 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve 7

g Size T

Safety)OM Act /j Norm ( Safety l Fail I'est Test CSJ/ROJ Nomenclature Flow Diagram . System B il A I I 1 Number Coord ,i(inch)

II Class', Cat,Pass Pos (

Pos,. Pos Type Freq RR ICS-9 Letdown Orifice Iso Vlv- 2165-S-1303 B-12 2060 2 GL AO 2 A Act 0/C C C FSC Q n/a Orifice "C" 60 GPM (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a ICT-102 Containment Sump to CS 2165-S-550 M-7 2070 12 GA MO 2 B Act C 0/C AI PIT 2YR n/a Pump "B" Iso Vlv (CIV) STC Q n/a STO Q n/a ICT-105 Containment Sump to CS 2165-S-550 N-7 2070 12 GA MO B Act C 0/C AI PIT 2YR n/a Pump "A" Iso Vlv (CIV) STC Q n/a STO Q n/a ICT-11 Containment Spray 2165-S-550 1-12 2070 2 GL MO B Act C 0/C AI PIT 2YR n/a Chemical Addition Iso Vlv STC Q n/a STO Q n/a ICT-12 Containment Spray 2165-S-550 H-12 2070 2 GL MO 3 B Act C 0/C Al PIT 2YR n/a Chemical Addition Iso Vlv STC Q n/a STO Q n/a ICT-24 Containment Spray Eductor 2165-S-550 H-14 2070 GL MO 2 B Act C C Al PIT 2YR n/a Test Iso Vlv STC Q n/a ICT-25 Containment Spray Eductor 2165-S-550 H-14 2070 GL MO B Act C C Al PIT 2YR n/a Test Iso Vlv STC Q n/a ICT-26 RWST to Containment 2165-S-550 F-15 2070 12 GA MO B Act 0 0/C AI PIT 2YR n/a Spray Pump "A" Iso Vlv STC n/a Q

I CT-27 RWST to Containment 2165-S-550 F-14 2070 12 CK SA 2 C Act C 0/C n/a SC Q n/a Spray Pump "A" Check Vlv SO Q n/a ICT-47 Containment Spray Pump 2165-S-550 E-5 2070 6 GA MO B Act C C Al PIT 2YR n/a "A" Test Line to RWST Iso STC n/a Q

Vlv ICT-5 Containment Spray Add. 2165-S-550 B-9 2070 I X1.5 RV SA 3 C Act C 0/C n/a SP 10YR n/a Tank Relief Vlv Revision 0 Page46 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve Dwg System Size Body.Actuator'Safety. 0MAct/ Norm )Safety Fail 'est '.

Test CSJ/ROJ I

Number Nomenclature Flow Diagram

,Coord'(inch)'lass'at'Pass

~

Pos "

Pos Pos ,Type Freq RR ICT-50 Containment Spray Pump 2165-S-550 F-4 2070 8 GA MO 2 A Act C 0/C Al LJ 2YR n/a "A" Disch to Nozzles Iso PIT 2YR n/a Vlv (CIV) STC Q n/a STO Q n/a ICT-53 Containment Spray Pump 2165-S-550 F-3 2070 8 CK SA 2 A/C Act C 0/C n/a LJ 2YR n/a "A" Disch to Nozzles Check SC RO CT-ROJ I Vlv (CIV) SDIS RO CT-VR I I CT-62 CS Pump "A" Chemical 2165-S-550 H-7 2070 2 CK SA 2 C Act C 0/C n/a SC Q n/a Addition Check Vlv SO Q n/a ICT-65 CS Pump "B" Chemical 2165-S-550 J-7 2070 CK SA 2 C Act C 0/C n/a SC Q n/a Addition Check Vlv SO Q n/a ICT-71 RWST to Containment 2165-S-550 K-16 2070 12 GA MO 2 B Act 0 0/C AI PIT 2YR n/a Spray Pump "B" Iso Vlv STC Q n/a ICT-72 RWST to Containment 2165-S-550 K-15 2070 12 CK SA 2 C Act C 0/C n/a SC Q n/a Spray Pump "B" Check Vlv SO Q n/a ICT-88 Containment Spray Pump 2165-S-550 K-4 2070 8 GA MO 2 A Act C 0/C AI LJ 2YR n/a "B" Disch to Nozzles Iso PIT 2YR n/a Vlv (CIV) STC Q n/a STO Q n/a ICT-91 Containment Spray Pump 2165-S-550 K-3 2070 8 CK SA 2 A/C Act C 0/C n/a LJ 2YR n/a "B" Disch to Nozzles Check SC RO CT-ROJ I Vlv (CIV) SDIS RO CT-VR I ICT-95 Containment Spray Pump 2165-S-550 L-5 2070 6 GA MO 2 B Act C C Al PIT 2YR n/a "B" Test Line to RWST Iso STC n/a Q

Vlv ICT-E017 Containment Spray Add. 2165-S-550 A-8 2070 2 CK SA 3 C Act C 0/C n/a SP 10YR n/a Tank Vacuum Breaker ICT-E018 Containment Spray Add. 2165-S-550 A-8 2070 2 CK SA 3 C Act C 0/C n/a SP 10YR n/a Tank Vacuum Breaker ICZ-I Normal Air Intake Iso Vlv 2165-S-1017 F-2 8220 16 BF MO 3 B Act 0 C Al PIT 2YR n/a STC Q n/a Revision 0 Page47 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table T

Valve Nomenclature Flow Diagram I

' 'ystem I Size ~

Bod I'A I tor SafetytOM Act/I Norm Safety Fail Test Test 'SJ/ROJ (inch),,

~

Number ;Coordl

~

Class', Cat Pass

~

2 li Pos, Pos Pos Type Freq RR

,'L'2 ICZ-10 Emerg Filt South Outside 2165-S-1017 J-5 8220 BF MO 3 B Act C 0/C Al PIT 2YR n/a Air Inlet STC Q n/a STO Q n/a ICZ-11 Emerg Filt North Outside 2165-S-1017 J-8 8220 12 BF MO 3 B Act C 0/C AI PIT 2YR n/a Air Inlet STC Q n/a STO Q n/a ICZ-12 Emerg Filt North Outside 2165-S-1017 J-8 8220 12 BF MO 3 B Act C 0/C AI PIT 2YR n/a Air Inlet STC Q n/a STO Q n/a ICZ-13 Smoke Purge Exhaust Iso 2165-S-1017 B-3 8220 30 BF MO 3 B Act 0/C C AI PIT 2YR n/a Vlv STC Q n/a ICZ-14 Smoke Purge Exhaust Iso 2165-S-1017 B-4 8220 30 BF MO 3 B Act 0/C AI PIT 2YR n/a Vlv STC Q n/a ICZ-15 Emerg Filt Outside Air Inlet 2165-S-1017 1-6 8220 CK SA 3 C Act C 0 n/a SO Q n/a Check Vlv ICZ-16 Emerg Filt Outside Air Inlet 2165-S-1017 L-6 8220 6 CK SA 3 C Act C 0 SO n/a Check Vlv ICZ-17 Purge Makeup Intake Iso 2165-S-1017 F-I 8220 36 BF MO 3 B Act 0/C C Al PIT 2YR n/a Vlv STC Q n/a ICZ-18 Purge Makeup Intake Iso 2165-S-1017 F- I 8220 36 BF MO 3 B Act 0/C C Al PIT 2YR n/a Vlv STC Q n/a I CZ-19 Emergency Filtration 2165-S-1017 F-5 8220 20 BF MO 3 B Act C 0 AI PIT 2YR n/a Discharge Iso Vlv - Train STO Q n/a II AII I CZ-2 Normal Air Intake Iso Vlv 2165-S-1017 F-2 8220 16 BF MO 3 B Act 0 Al PIT 2YR n/a STC Q n/a ICZ-20 Emergency Filtration 2165-S-1017 F-6 8220 20 BF MO 3 B Act C 0 Al PIT 2YR n/a Discharge Iso Vlv - Train STO Q n/a ItBII ICZ-21 Emergency Filtration Fan R- 2165-S-1017 H-6 8220 20 BF MO 3 B Act C 0 Al PIT 2YR n/a 2-IA Discharge Iso Vlv STO Q n/a Revision 0 Page 4S of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve Nomenclature Flow Diagram System Size Body Actuator OM,Act /,, Norm 'afety Fail Test Test CSJ/ROJ Number ,'Coo rd ,(inch) Class Cat Pass Pos Pos Pos Type Freq RR ICZ-22 Emergency Filtration Fan R- 2165-S-1017 H-8 8220 20 BF MO 3 B Act C 0 Al PIT 2YR n/a 2-1 B Discharge Iso Vlv STO Q n/a ICZ-23 Emergency Filtration Fan R- 2165-S-1017 1-6 8220 20 BF MO 3 B Act C 0 Al PIT 2YR n/a 2-IA Inlet Iso Vlv STO Q n/a ICZ-24 Emergency Filtration Fan R- 2165-S-1017 1-9 8220 20 BF MO 3 B Act C 0 AI PIT 2YR n/a 2-1 B Inlet Iso Vlv STO Q n/a I CZ-25 Air Handling Unit AH 2165-S-1017 FA 8220 36 BF MO 3 B Act 0/C 0 Al PIT 2YR n/a IA Discharge Iso Vlv STO Q n/a ICZ-26 Air Handling Unit AH 2165-S-1017 G-4 8220 36 BF MO 3 B Act Olc Al PIT 2YR n/a IB Discharge Iso Vlv STO Q n/a ICZ-3 Normal Air Exhaust Iso Vlv 2165-S-1017 D-2 8220 12 BF MO 3 B Act, 0 Al PIT 2YR n/a STC Q n/a ICZ-32 RAB Elec Equip Rm Smoke 2165-S-1017 L-3 8210 36 BF MO 3 B Pass C Al PIT 2YR n/a Purge Makeup Inlet Iso Vlv ICZ-33 RAB Elec Equip Rm Smoke 2165-S-1017 L-3 8210 36 BF MO 3 B Pass C Al PIT 2YR n/a Purge Makeup Inlet Iso Vlv ICZ-34 RAB Elec Equip Rm Smoke 2165-S-1017 L-9 8210 30 BF MO 3 B Pass C Al PIT 2YR n/a Purge Inlet Iso Vlv ICZ-35 RAB Elec Equip Rm 2165-S-1017 L-9 8210 30 BF MO 3 B Pass C C AI PIT 2YR n/a Exhaust Discharge Iso Vlv ICZ-4 Normal Air Exhaust Iso Vlv 2165-S-1017 D-2 8220 12 BF MO 3 B Act 0 C AI PIT 2YR n/a STC Q n/a I CZ-5 RAB Elec Equip Rm OAI 2165-S-1017 M-2 8210 12 BF MO 3 B Act 0 AI PIT 2YR n/a Purge Inlet Iso Vlv STC Q n/a ICZ-6 RAB Elec Equip Rm OAI 2165-S-1017 M-3 8210 12 BF MO 3 B Act 0 C Al PIT 2YR n/a Purge Inlet Iso Vlv STC Q n/a ICZ-7 RAB Elec Equip Rm 2165-S-1017 L-6 8210 12 BF MO 3 B Act 0 AI PIT 2YR n/a Exhaust Discharge Iso Vlv STC Q n/a ICZ-8 RAB Elec Equip Rm 2165-S-1017 L-6 8210 12 BF MO 3 B Act 0 Al PIT 2YR n/a Exhaust Discharge Iso Vlv STC Q n/a Revision 0 Page49 of 145

0 HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table a= T r Valve (Dwg System

) Size,) Body ',,'Actuator Safety~ OM Act /tl Norm ISafety I Fail Test Test CSJ/ROJ Number Nomenclature Flow Diagram Coo rd',

1

]i(inch)] '(Classy

, Cat Pass[ Pos Pos Pos 'Type Freq- RR ICZ-9 Emerg Filt South Outside 2165-S-1017 J-5 8220 12 BF MO 3 B Act 0/C Al PIT 2YR n/a Air Inlet STC Q n/a STO Q n/a ID FO-168 F.O. Transfer Pump "IA" 2165-S-563 G 2 5100 2 CK, SA 3 C Act C 0/C n/a SC Q n/a Discharge Check Vlv SO Q n/a I DFO-170 F.O. Transfer Pump "IA" 2165-S-563 G- I 5100 .75X I RV SA 3 C Act C 0/C n/a SP IOYR n/a Discharge Relief Vlv I DFO-173 F.O. Day Tank "IA"Inlet 2165-S-633 S03 A-6 5100 2 GL SO 3 B Act 0/C 0/C 0 FSO Q n/a Iso Vlv PIT 2YR n/a STC Q n/a STO Q n/a I DFO-176 EDG "IA"Fuel Oil 2165-S-633 S03 A-10 5100 1.5 RV SA 3 C Act 0/C n/a SP IOYR n/a Circulating Hdr. Relief Vlv I DFO-186 F.O. Transfer Pump "IB" 2165-S-563 G-7 5100 2 CK SA 3 C Act C 0/C n/a SC Q n/a Discharge Check Vlv SO Q n/a ID FO-188 F.O. Transfer Pump "I B" 2165-S-563 G-5 5100 .75X I RV SA 3 C Act C 0/C n/a SP IOYR n/a Discharge Relief Vlv ID FO-191 F.O. Day Tank "IB" Inlet 2165-S-633 S03 H-6 5100 2 GL SA 3 B Act C 0/C 0 FSO Q n/a lso Vlv PIT 2YR n/a STC Q n/a STO Q n/a I DFO-194 EDG "IB" Fuel Oil 2165-S-633 S03 H-10 5100 1.5 RV SA 3 C Act C 0/C n/a SP IOYR n/a Circulating Hdr. Relief Vlv I DFO-214 DFO Transre Pump I A-SA 2165-S-563 F-2 5100 2 GA SA 3 B Act LC 0 n/a SO n/a Suction Strainer Bypass I DFO-215 DFO Transre Pump I B-SB 2165-S-563 F-7 5100 2 GA MAN 3 B Act LC 0 n/a SO n/a Suction Strainer Bypass IDW-15 Demin Water Make-up Vlv 2165-S-1319 F-2 4080 3 DA AO 3 B Pass C C n/a PIT 2YR n/a to CCW Pump Suction ID W-63 Demin Water Supply to 2165-S-799 H-5 6270 3 GA MAN 2 A Pass LC C n/a LJ 2YR n/a Primary Cont. (CIV)

Revision 0 Page50 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table

'f Valve Nomenclature Flow Diagram wg 'System t . Body ~Actuatorj(SafetgOM Act/ Norm ( Safety Fail, Test Test

~

CSJ/ROJ Pos 'ype" Freq T'os

) ,

Number f(inch) [

'Coordl

~Class~Cat Pass~ Pos RR I DW-65 Demin Water Supply to 2165-S-799 H-6 6270 3 CK SA 2 A/C Act C 0/C n/a LJ 2YR n/a Primary Cont. (CIV) SC RO DW-ROJ I SO RO DW-ROJ I I EA-19 Starting AirTank "IB" Inlet 2165-S-633 S04 F-11 5112 1.5 CK SA 3 C Act 0/C C n/a SC Q n/a Check Vlv I EA-21 Starting AirTank "I B" 2165-S-633 S04 E-12 5112 1.5 RV SA 2 C Act C 0/C n/a SP IOYR n/a Relief Vlv I EA-35 Starting AirTank "IC" Inlet 2165-S-633 S04 J-11 5112 1.5 CK SA 3 C Act 0/C C n/a SC Q n/a Check Vlv I EA-37 Starting AirTank "IC" 2165-S-633 S04 H-12 5112 1.5 RV SA 3 C Act C 0/C n/a SP 10YR n/a Relief Vlv IEA-4 Starting AirTank "IA"Inlet 2165-S-633 S04 C-11 5112 1.5 CK SA 3 C Act 0/C C n/a SC Q n/a Check Vlv I EA-50 Starting AirTank "ID" Inlet 2165-S-633 S04 M-11 5112 1.5 CK SA 3 C Act 0/C C n/a SC Q n/a Check Vlv I EA-52 Starting Air Tank "ID" 2165-S-633 S04 L-12 5112 1.5 RV SA 3 C Act C 0/C n/a SP 10YR n/a Relief Vlv I EA-6 Starting AirTank "IA" 2165-S-633 S04 A-12 5112 1.5 RV SA 3 C Act C 0/C n/a SP 10YR n/a Relief Vlv I ED-119 RCDT Pump Disch Bypass 2165-S-1313 E-17 6240 3 DA MAN 2 A Pass LC C n/a -

LJ 2YR n/a Iso Vlv (CIV)

I ED-121 RCDT Pump Disch Level 2165-S-1313 E-16 6240 3 GL AO 2 A Act 0 C FSC Q n/a Control Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a I ED-125 RCDT Pump Disch Iso Vlv 2165-S-1313 D-16 6240 3 DA AO 2 A Act 0 C C FSC Q n/a (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a Revision 0 Page51 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5,3 Valve Table Valve Nomenclature Flow Diagram System ) Body I I'afety] OM [ Act /f Norm l Safety Fail I Test -'est CSJ/ROJ Number Coord, (inch) t 1 Class".Cat!Pass! Pos ~

Pos Pos Type Freq RR 1ED-161 RCDT Hydrogen 2165-S-1313 C-7 6240 0.75 DA AO 2 A Act 0 C C FSC Q n/a Connection Iso Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a 1ED-164 RCDT Hydrogen 2165-S-1313 E-6 6240 0.75 DA AO 2 A Act 0 C C FSC Q n/a Connection Iso Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a I ED-94 Containment Sump Disch. 2165 S 685 M7 6240 3 GA MO 2 A Act 0 C Al LJ 2YR n/a Iso Vlv (CIV) PIT 2YR n/a STC Q n/a I ED-95 Containment Sump Disch. 2165-S-685 M-7 6240 3 GA MO 2 A Act 0 C Al LJ 2YR n/a Iso Vlv (CIV) PIT 2YR n/a STC Q n/a I FP-347 Fire Water Sprinkler Supply 2165-S-888 L-2 6175 8 GL AO 2 A Act 0 C C FSC Q n/a Iso Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a 1FP-349 Fire Water Sprinkler Supply 2165-S-888 L-3 6175 6 CK SA 2 A/C Act C 0/C n/a LJ 2YR n/a Check Vlv (CIV) SC RO FP-ROJ I SO RO FP-ROJ I 1FP-355 Fire Water Standpipe 2165-S-888 M-2 6175 4 GA MAN 2 A Pass LC C n/a LJ 2YR n/a Supply Iso Vlv (CIV) 1FP-357 Fire Water Standpipe 2165-S-888 L-3 6175 4 CK SA 2 A/C Act C 0/C n/a LJ 2YR n/a Supply Check Vlv (CIV) SC RO FP-ROJ I SO RO FP-ROJ I 1FV-2 Inlet Iso Vlv From FHB to 2165-S-1017 N-14 8352 24 BF MO 3 B Act C 0 Al PIT 2YR n/a Emergency Exhaust Fan E- STO Q n/a 12-SA Revision 0 Page 52 of 145

HNP-IST-002 HNP IST Program Plan -2nd Interval 5.3 Valve Table

'I Valve Nomenclature

'Dw Flow Diagram,'g,, System j Size Bod A Safety'OM Act/ Norm 'Safety. Fail Test Test CSJ/ROJ Number >Coo rdt ~(inch);. >l Class, CatiPass I Pos Pos Pos 'ype Freq RR I FV-4 Inlet Iso Vlv From FHB to 2165-S-1017 M-14 8352 24 BF MO 3 B Act C 0 AI PIT 2YR n/a Emergency Exhaust Fan E- STO Q n/a 13-SB IFW-158 Feedwater Injection Check 2165-S-544 B-7 3050 16 CK SA 2 C Act 0 C n/a SC CS FW-CSJ2 Vlv to S/G "A" I FW-159 Feedwater Line Iso Vlv to 2165-S-544 B-6 3050 16 GA EH 2 B Act 0 C FSC CS FW-CSJ I S/G "A" (CIV) PIT 2YR n/a PSC Q FW-CSJ I STC CS FW-CSJ I I FW-163 "A" SG Ammonia Addition 2165-S-544 B-6 3050 GL AO 2 B Act 0/C C FSC Q n/a to FW Iso Vlv (CIV) PIT 2YR n/a STC Q n/a I FW-165 "A" SG Hydrazine Addition 2165-S-544 B-5 3050 I GL AO 2 B Act 0/C C FSC Q n/a to FW Iso Vlv (CIV) PIT 2YR n/a STC Q n/a I FW-216 Feedwater Injection Check 2165-S-544 D-5 3050 16 CK SA 2 C Act 0 C SC CS FW-CSJ2 Vlv to S/G "C" IFW-217 Feedwater Line Iso Vlv to 2165-S-544 D-4 3050 16 GA EH 2 B Act 0 C FSC CS FW-CSJ I S/G "C" (CIV) PIT 2YR n/a PSC Q FW-CSJ I STC CS FW-CSJ I IF W-221 "C" SG Ammonia Addition 2165-S-544 D-4 3050 I GL AO 2 B Act 0/C C FSC Q n/a to FW Iso Vlv (CIV) PIT 2YR n/a STC Q n/a I FW-223 "C" SG Hydrazine Addition 2165-S-544 D-3 3050 I GL AO 2 B Act 0/C C C FSC Q n/a to FW Iso Vlv(CIV) PIT 2YR n/a STC Q n/a I FW-276 Feedwater Injection Check 2165-S-544 E-4 3050 16 CK SA 2 C Act 0 C n/a SC CS FW-CSJ2 Vlv to S/G "B" Revision 0 Page53 of 145

HNP-IST-002 HNP IST Program Plan -2nd Interval 5.3 Valve Table Valve Nomenclature Flow Diagram System Size Body Actuator Safety OM, Act /, Norm 'afety Fail Test Test CSJ/ROJ Number Coord (inch) Class Cat Pass Pos Pos Pos Type Freq RR IF W-277 Feedwater Line Iso Vlv to 2165-S-544 E-4 3050 16 GA EH B Act 0 C C FSC CS FW-CSJ I S/G "B" (CIV) PIT 2YR n/a PSC Q FW-CSJ I STC CS FW-CSJ I I FW-279 "B" SG Ammonia Addition 2165-S-544 E-4 3050 I GL AO 2 B Act 0/C C FSC n/a Q

to FW Iso Vlv(CIV) PIT 2YR n/a STC n/a IF W-281 "B" SG Hydrazine Addition 2165-S-544 E-3 3050 I GL AO 2 B Act 0/C C C FSC n/a Q

to FW Iso Vlv (CIV) PIT 2YR n/a STC Q n/a 1FW-307 "A" SG FW Bypass Iso Vlv 2165-S-544 B-6 3050 3 GL AO 2 B Act 0/C C FSC Q n/a (CIV) PIT 2YR n/a STC Q n/a 1FW-313 "C" SG FW Bypass Iso Vlv 2165-S-544 D-4 3050 3 GL AO 2 B Act 0/C C FSC Q n/a (CIV) PIT 2YR n/a STC Q n/a I FW-319 "B" SG FW Bypass Iso Vlv 2165-S-544 F-4 3050 3 GL AO 2 B Act 0/C C C FSC Q n/a (CIV) PIT 2YR n/a STC Q n/a 11A-220 Instrument Air Supply to 2165-S-801 D-12 6135 3 CK SA 2 A/C Act 0 C n/a LJ 2YR n/a Containment Check Vlv SC RO IA-ROJ I (CIV)

I IA-786 Instrument Air Supply 2165-S-1017 G-13 6135 0.75 CK SA 2 C Act 0/C C n/a SC RO IA-VRI Check to Accum. Tk. IA-SA (Series with I IA-787)

I IA-787 Instrument Air Supply 2165-S-1017 G-3 6135 0.75 CK SA 2 C Act 0/C C n/a SC RO IA-VRI Check to Accum. Tk. IA-SA (Series with I IA-786) 1IA-788 Instrument Air Supply 2165-S-1017 H-13 6135 0.75 CK SA 2 C Act 0/C C n/a SC RO IA-VRI Check to Accum. Tk. I B-SB (Series with I IA-789)

Revision 0 Page 54 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve Nomenclature Dwg S Size B d Actuato Safety OM Act/ Norm 'Safety Fail Test Test CSJ/ROJ Number Coord (inch) Class Cat Pass Pos Pos Pos Type Freq RR I IA-789 Instrument Air Supply 2165-S-1017 H-13 6135 0.75 CK SA 2 C Pass 0/C C n/a SC RO IA-VRI Check to Accum. Tk. IB-SB (Series with I IA-788)

I IA-819 Instrument Air Supply to 2165-S-801 C-3 6135 3 GL AO 2 A Act 0 C C FSC CS IA-CSJ I Containment Iso Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC CS IA-CSJ I 1LT-0004 Containment ILRT Iso Vlv 2166-S-916 D-4 8070 8 GA MAN 2 A Pass LC C LJ 2YR n/a (CIV) 1LT-0006 Containment ILRT Iso Vlv 2166-S-916 D-6 8070 I GL MAN 2 A Pass LC C LJ 2YR n/a (CIV) 1LT-0010 Containment ILRT Iso Vlv 2166-S-916 D-6 8070 I GL MAN 2 A Pass LC C LJ 2YR n/a (CIV)

I MS-231 MS Hdr "A" Drip Leg 2165-S-542 E-8 3020 2 GL AO 2 B Act 0/C C FSC Q n/a Drain Iso Vlv (CIV) PIT 2YR n/a STC Q n/a I MS-25 MS Line "A" to Sampling 2165-S-542 D-2 3020 I GL AO 2 B Act 0 C C FSC Q n/a System (CIV) PIT 2YR n/a STC Q n/a I MS-266 MS Hdr "B" Drip Leg Drain 2165-S-542 1-8 3020 2 GL AO 2 B Act 0/C C C FSC Q n/a Iso Vlv (CIV) PIT 2YR n/a STC Q n/a I MS-27 MS Line "B" to Sampling 2165-S-542 G-2 3020 I GL AO 2 B Act 0 C FSC Q n/a System (CIV) PIT 2YR n/a STC Q n/a I MS-29 MS Line "C" to Sampling 2165-S-542 K-2 3020 I GL AO 2 B Act 0 C C FSC Q n/a System (CIV) PIT 2YR n/a STC Q n/a 1MS-301 MS Hdr "C" Drip Leg Drain 2165-S-542 L-8 3020 2 GL AO 2 B Act 0/C C FSC Q n/a Iso Vlv (CIV) PIT 2YR n/a STC Q n/a Revision 0 Page55 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table j

Safety" OM i Act /'Norm Safety

~ I Valve Flow Diagram "g System Size Body Actuatorl Fail Test Test CSJ/ROJ Nomenclature

'lass j Cat Jt Pass j Pos [ Pos

~

) I Number ,Coord ,(inch) ,'

~ Pos Type Freq RR I 4 I MS-336 AFWPT Stm Supply Drip 2165-S-542 M-4 3020 GL AO 2 B Pass LO 0 n/a PIT 2YR n/a Leg Drain Iso Vlv I MS-354 AFWPT Stm Supply Drip 2165-S-542 N-5 3020 2 GL AO 2 B Pass LO 0 n/a PIT 2YR n/a Leg Drain Iso Vlv I MS-43 Main Steam Line ".A" 2165-S-542 C-3 3020 6X10 RV SA 2 C Act C 0/C n/a SP SYR n/a Safety Vlv (CIV)

I MS-44 Main Steam Line "B" 2165-S-542 G-3 3020 6X10 RV SA 2 C Act C 0/C n/a SP 5YR n/a Safety Vlv (CIV)

I MS-45 Main Steam Line "C" 2165-S-542 J-3 3020 6X I 0 RV SA 2 C Act C 0/C n/a SP 5YR n/a Safety Vlv (CIV)

I MS-46 Main Steam Line "A" 2165-S-542 C-4 3020 6X I 0 RV SA 2 C Act C 0/C n/a SP SYR n/a Safety Vlv (CIV)

I MS-47 Main Steam Line "B" 2165-S-542 G-4 3020 6X 10 RV SA 2 C Act C 0/C n/a SP 5YR n/a Safety Vlv (CIV)

I MS-48 Main Steam Line "C" 2165-5-542 3-4 3020 6XI 0 RV SA 2 C Act C 0/C n/a SP SYR n/a Safety Vlv (CIV)

I MS-49 Main Steam Line "A" 2165-S-542 C-5 3020 6X IO RV SA 2 C Act C 0/C n/a SP SYR n/a Safety Vlv (CIV)

I MS-50 Main Steam Line "B" 2165-S-542 G-5 3020 6X I 0 RV SA 2 C Act C 0/C n/a SP 5YR n/a Safety Vlv (CIV)

I MS-51 Main Steam Line "C" 2165-S-542 J-5 3020 6X10 RV SA 2 C Act C 0/C n/a SP SYR n/a Safety Vlv (CIV)

I MS-52 Main Steam Line "A" 2165-S-542 C-6 3020 6X I 0 RV SA 2 C Act C 0/C n/a SP 5YR n/a Safety Vlv (CIV)

I MS-53 Main Steam Line "B" 2165-S-542 G-6 3020 6X IO RV SA 2 C Act C 0/C n/a SP 5YR n/a Safety Vlv (CIV)

I MS-54 Main Steam Line "C" 2165-S-542 J-6 3020 6X I 0 RV SA 2 C Act C 0/C n/a SP 5YR n/a Safety Vlv (CIV)

I MS-55 Main Steam Line "A" 2165-S-542 C-6 3020 6X10 RV SA 2 C Act C 0/C n/a SP SYR n/a Safety Vlv (CIV)

Revision 0 Page56 of 145

t

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve Number Flow Diagram 'g Coord',

System (inch) il, 1

,Actuator!Safety OM Act /~ Norm ( Safety l Class Cat Pass I Pos Pos

'I Fail Pos Test Test Type Freq CSJ/ROJ RR L I =! l l I MS-56 Main Steam Line "B" 2165-S-542 G-6 3020 6X10 RV SA 2 C Act C 0/C n/a SP SYR n/a Safety Vlv (CIV)

I MS-57 Main Steam Line "C" 2165-S-542 J-6 3020 6X I 0 RV SA 2 C Act C 0/C n/a SP 5YR n/a Safety Vlv (CIV)

I MS-58 MS Line "A" PORV (CIV) 2165-S-542 C-8 3020 8 GL EH 2 B Act C 0/C C FSC Q n/a PIT 2YR n/a STC Q n/a STO Q n/a I MS-59 MS Line "A" PORV Block 2165-S-542 C-8 3020 8 GA MAN 2 B Act 0 0/C n/a SC Q n/a Vlv I MS-60 MS Line "B" PORV (CIV) 2165-S-542 F-8 3020 8 GL EH 2 B Act C 0/C C FSC Q n/a PIT 2YR n/a STC Q n/a STO Q n/a I MS-61 MS Line "B" PORV Block 2165-S-542 G-8 3020 8 GA MAN 2 B Act 0 0/C n/a SC Q n/a Vlv I MS-62 MS Line "C" PORV (CIV) 2165-S-542 J-8 3020 8 GL EH 2 B Act C 0/C C FSC Q n/a PIT 2YR n/a STC Q n/a STO Q n/a I MS-63 MS Line "C" PORV Block 2165-S-542 J-8 3020 8 GA MAN 2 B Act 0 0/C n/a SC Q n/a Vlv I MS-70 MS "B" to AFW Turbine 2165-S-542 H-7 3020 6 GA MO 2 B Act C 0/C Al PIT 2YR n/a Block Vlv (CIV) STC Q n/a STO Q n/a I MS-71 MS "B" to AFW Turbine 2165-S-542 H-7 3020 6 CK SA 3 C Act C 0/C n/a PSO Q MS-CSJ2 Check Vlv SDIS RO MS-VRI SO CS MS-CSJ2 I MS-72 MS "C" to AFW Turbine 2165-S-542 K-7 3020 6 GA MO 2 B Act C 0/C AI PIT 2YR n/a Block Vlv (CIV) STC Q n/a STO Q n/a Revision 0 Page57 of 145

BI HNP-IST-002 HNP IST Program Plan -2nd Interval 5.3 Valve Table Valve Dwwg ~ System ~SIze I B d Il'Actuator)Safety OM Act /I) Norm 'i Safety Fail ;'Test Test CSJ/ROJ Nomenclature Flow Diagram )

Number Coord j(inch) ~

Class Cat Pass "

Pos Pos Pos Type Freq RR I MS-73 MS "C" to AFW Turbine 2165-S-542 K-7 3020 6 CK SA 3 C Act 0/C n/a PSO Q MS-CSJ2 Check Vlv SDIS RO MS-VR I SO CS MS-CSJ2 IMS-80 Main Steam Iso Vlv 2165-S-542 D-9 3020 32 GL AO 2 B Act 0 C C FSC CS MS-CSJ I (MSIV) for MS Hdr "A" PIT 2YR n/a (CIV) PSC Q MS-CSJ I STC CS MS-CSJ I I MS-81 MS Hdr "A" MSIV Bypass 2165-S-542 D-9 3020 3 GL AO 2 B Act 0/C C C FSC Q n/a Iso Vlv (CIV) PIT 2YR n/a STC Q n/a I MS-82 Main Steam Iso Vlv 2165-S-542 G-9 3020 32 GL AO 2 B Act 0 C C FSC CS MS-CSJ I (MSIV) for MS Hdr "B" PIT 2YR n/a (CIV) PSC Q MS-CSJ I STC CS MS-CSJ I I MS-83 MS Hdr "B" MSIV Bypass 2165-S-542 H-9 3020 3 GL AO 2 B Act 0/C C C FSC Q n/a Iso Vlv (CIV) PIT 2YR n/a STC Q n/a I MS-84 Main Steam Iso Vlv 2165-S-542 J-9 3020 32 GL AO 2 B Act 0 C C FSC CS MS-CSJ I (MSIV) for MS Hdr "C" PIT 2YR n/a (CIV) PSO Q MS-CSJI STC CS MS-CSJ I I MS-85 MS Hdr "C" MSIV Bypass 2165-S-542 K-9 3020 3 GL AO 2 B Act 0/C C C FSC Q n/a Iso Vlv (CIV) PIT 2YR n/a STC Q n/a I MS-E018 TDAFW Pump Turbine 2165-S-542 N-3 3020 16 RD SA 3 D Act C 0/C n/a SP 5YR n/a Rupture Disc I MS-G AFWP Turbine Governing 2165 S 542 N I 3020 4 GL EH 3 B Act 0 T 0 SKID Q n/a Vlv I MS-T AFWP Turbine Trip 2165-S-542 N-I 3020 4 GL MO 3 B Act 0 0/C 0 SKID Q n/a Throttle Vlv Revision 0 Page5S of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve Nomenclature Flow Diagram [

" l System Size Body Actuato Safety OM Act I Norm Safety Fail ', Test. Test '-'os CSJ/ROJ Number Coord) (inch) Class Cat Pass Pos Pos > Type', Freq RR I RC-1003 PORV N2/Air Accum. Tank 2165-S-1309 B-9 2050 IX2 RV SA 3 A/C Act C 0/C n/a LK 2YR n/a IA-SA Relief Vlv SP IOYR n/a I

I RC-1004 PORV N2/Air Accum. Tank 2165-S-1309 A-9 2050 IX2 RV SA 3 A/C Act . C 0/C n/a LK 2YR n/a IC-SB Relief Vlv SP 10YR n/a I RC-113 PRZ PORV "I RC-114" 2165-S-1301 H-2 2050 3 GA MO I B -Act 0 0/C Al PIT 2YR n/a Block Vlv STC Q n/a STO Q n/a I RC-114 PRZ PORV PCV-444B 2165-S-1301 H- I 2050 3 GL AO I B Act C 0/C C FSC CS RC-CSJ I PIT 2YR n/a STC CS RC-CSJ I STO CS RC-CSJ I I RC-I I5 ~

PRZ PORV "IRC-116" 2165-S-1301 F-2 2050 3 GA MO I B Act 0 C Al PIT 2YR n/a Block Vlv STC Q n/a STO Q n/a I RC-116 PRZ PORV PCV-445B 2165-S-1301 F-I 2050 3 -GL AO I B Act C C FSC CS RC-CSJ I PIT 2YR n/a STC CS RC-CSJ I STO CS RC-CSJ I

. IRC-117 PRZ PORV "IRC-118" 2165-S-1301 E-2 2050 3 GA MO I B Act 0 0/C AI PIT 2YR n/a Block Vlv STC Q n/a STO Q n/a IRC-118 PRZ PORV PCV-445A 2165-S-1301 E-I 2050 3 GL AO I B Act C 0/C C FSC CS RC-CSJ I PIT 2YR n/a STC CS RC-CSJ I STO CS RC-CSJ I IRC-123 PRZ Safety Vlv 2165-S-1301 F4 2050 6X6 RV SA I C Act C 0/C n/a SP SYR n/a I RC-125 PRZ Safety Vlv 2165-S-1301 F-6 2050 6X6 RV SA I C Act C 0/C n/a SP SYR n/a I RC-127 PRZ Safety Vlv 2165-S-1301 F-8 2050 6X6 RV SA I C Act C 0/C n/a SP SYR n/a J

Revision 0 Page59 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table I

Valve I OMIAct /'orm Safety, Fail Test Test CSJ/ROJ "g System Nomenclature Flow Diagram Body Actuator

'os I

I Safety'inch)

Number Coord I Class, Cat.Pass Pos Pos Type Freq RR 1RC-141 N2 Supply to PRT Iso Vlv 2165-S-1301 C-16 2050 I DA AO 2 A Act C C C FSC Q n/a (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a 1RC-144 N2 Supply to PRT Iso Vlv 2165-S-1301 C-17 2050 I DA AO 2 A Act C C C FSC Q n/a (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a I RC-161 RMW to PRT Iso Vlv (CIV) 2165-S-1301 D-17 2050 3 DA AO 2 A Act 0 C C FSC Q n/a LJ 2YR n/a PIT 2YR n/a STC Q n/a I RC-164 RMW to PRT Iso Vlv (CIV) 2165-S-1301 D-16 2050 3 CK SA 2 A/C Act 0/C 0/C n/a LJ 2YR n/a SC RO RC-ROJ I SO Q n/a I RC-174 N2 Inlet Check Vlv to 2165-S-1309 B-9 2050 I CK SA 3 A/C Act 0/C C n/a LK 2YR n/a PORV N2/Air Accum. Tank SC RO RC-ROJ2 IA-SA I RC-176 N2 Inlet Check Vlv to 2165-S-1309 A-9 2050 I CK SA 3 A/C Act 0/C C n/a LK 2YR n/a PORV N2/Air Accum. Tank SC RO RC-ROJ2 I C-SB I RC-900 Reactor Vessel Head Vent 2165-S-1301 A-7 2050 I GL SO 2 B Act C 0/C C FSC CS RC-CSJ2 Vlv PIT 2YR n/a STC CS RC-CS J2 STO CS RC-CSJ2 IRC-901 Reactor Vessel Head Vent 2165-S-1301 A-7 2050 I GL SO 2 B Act C 0/C C FSC CS RC-CSJ2 Vlv PIT 2YR n/a STC CS RC-CSJ2 STO CS RC-CS J2 Revision 0 Page 60 of 145

HNP-IST-002 HNP IST Program Plan -2nd Interval 5.3 Valve Table System Size Body Actuator Safety'; OM Act/ Norm, Safety;,

Valve Nomenclature D Fail Test Test CSJ/ROJ Flosv Diagram Number Coordi (inch)~ I, Class Cat Pass l',

Pos Pos Pos ~

Type Frcq RR 1

1RC-902 Pressurizer Steam Space 2165-S-1301 C-7 2050 I GL SO 2 B Act C 0/C C FSC CS RC-CSJ2 Vent Vlv PIT 2YR n/a STC CS RC-CSJ2 STO CS RC-CSJ2 1RC-903 Pressurizer Steam Space 2165-S-1301 B-7 2050 I GL SO 2 B Act C 0/C C FSC CS RC-CSJ2 Vent Vlv PIT 2YR n/a STC CS RC-CSJ2 STO CS RC-CSJ2 I RC-904 Vent Path to the 2165-S-1301 C-5 2050 I GL SO 2 B Act C 0/C C FSC CS RC-CSJ2 Containment Atmosphere PIT 2YR n/a STC CS RC-CSJ2 STO CS RC-CSJ2 IRC-905 Vent Path to the PRT 2165-S-1301 A 8 2050 I GL SO 2 B Act C 0/C C FSC CS RC-CSJ2 PIT 2YR n/a STC CS RC-CSJ2 STO CS RC-CSJ2 I RH-I RCS Loop I-HL to RHR 2165-S-1324 L-3 2085 12 GA MO I A Act C 0/C Al LK 2YR n/a Pump A-SA Iso Vlv (PIV) PIT 2YR n/a (CIV) STC CS RH-CSJI STO CS RH-CSJI I RH-120 RHR Train "B" Inlet Piping 2165-S-1324 1-4 2085 0.75 RV SA I C Act C 0/C n/a SP IOYR n/a Relief Vlv I RH-121 RHR Train "A" Inlet Piping 2165-S-1324 L-4 2085 0.75 RV SA I C Act C 0/C SP IOYR n/a Relief Vlv 1RH-16 RHR Pump "A"to PASS 2165-S-1324 L-14 2085 0.75 GL SO 2 B Pass C C PIT 2YR n/a Iso Vlv I RH-2 RCS Loop I-HL to RHR 2165-S-1324 L-4 2085 12 GA MO I A Act C 0/C AI LK 2YR n/a Pump A-SA Iso Vlv (CIV) PIT 2YR n/a (PIV) STC CS RH-CSJ I STO CS RH-CSJ I Revision 0 Page61 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table II Valve Nomenclature Flow Diagram wg S stem Bod Aetna Safety'M '*Act / 'Norm

, Safety Fail Test Test CSJ/ROJ Number Coord (inch) Class Cat: Pass Pos Pos Pos Type Freq RR IRH-20 RHR Htx "A" Bypass Flow 2165-S-1324 D-11 2085 8 BF AO 2 B Act 0/C C C FSC Q n/a Control Vlv PIT 2YR n/a STC Q n/a IRH-25 CSIP Suction Supply Iso 2165-S-1324 C-12 2085 GA MO 2 B Act C 0/C Al PIT 2YR n/a Vlv From RHR Htx "A" STO Q n/a I RH-30 RHR Htx "A" Outlet Flow 2165-S-1324 C-11 2085 10 BF AO 2 B Act 0/C 0 0 FSO Q n/a Control Vlv PIT 2YR n/a STO n/a I RH-31 RHR Pump "A" Min Flow 2165-S-1324 G-7 2085 3 GA MO 2 B Act 0 0/C Al PIT 2YR n/a Line Iso Vlv STC Q n/a STO Q n/a IRH-34 RHR Header "A" Discharge 2165-S-1324 C-7 2085 10 CK SA 2 C Act C 0/C n/a SC Q n/a Check Vlv SO Q n/a IRH-39 RCS Loop 3-HL to RHR 2165-S-1324 1-3 2085 12 GA MO I A Act C 0/C AI LK 2YR n/a Pump B-SB Iso Vlv PIT 2YR n/a (CIV)(PIV) STC CS RH-CSJI STO CS RH-CSJI IRH-40 RCS Loop 3-HL to RHR 2165-S-1324 1-4 2085 12 GA MO I A Act C 0/C Al LK 2YR n/a Pump B-SB Iso Vlv PIT 2YR n/a (CI V)(PIV) STC CS RH-CSJI STO CS RH-CSJ I I RH-45 RHR Pump I B-SBA 2165-S-1324 H-6 2085 3 RV SA 2 C Act C 0/C n/a SP IOYR n/a Suction Relief Vlv (CIV)

IRH-54 RHR Pump "B" to PASS 2165-S-1324 H-14 2085 0.75 GL SO B Pass C C C PIT 2YR n/a Iso Vlv IRH-58 RHR Htx "B" Bypass Iso 2165-S-1324 G-13 2085 8 BF AO 2 B Act 0/C C FSC Q n/a Vlv PIT 2YR n/a STC Q n/a IRH-63 CSIP Suction Supply Iso 2165-S-1324 F-12 2085 8 GA MO B Act C 0/C AI - PIT 2YR n/a Vlv From RHR Htx "B" STO Q n/a Revision 0 Page62 of 145

0 HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve Nomenclature Flow Diagram ;Dwg Size B d .A t t Safety'OM Act/, Norm Safety Fail 'est Test CSJ/ROJ Number rdl

'oo

"(inch) - 'lass" Cat Pass', Pos i Pos l Pos i Type Freq RR IRH-66 RHR Htx "B" Outlet Flow 2165-S-1324 E-I I 2085 10 BF AO 2 B Act 0/C 0 0 FSO Q n/a Control Vlv PIT 2YR n/a STO Q n/a IRH-69 RHR Pump "B" Min Flow 2165-S-1324 G-8 2085 3 GA MO 2 B Act 0 0/C Al PIT 2YR n/a Line Iso Vlv STC Q n/a STO Q n/a I RH-7 RHR Pump I A-SA Suction 2165-S-1324 K-6 2085 3 RV SA 2 C Act C 0/C n/a SP 10YR n/a Relief Vlv (CIV)

I RH-70 RHR Header "B" Discharge 2165-S-1324 F-8 2085 10 CK SA 2 C Act C 0/C n/a SC Q n/a Check Vlv SO Q n/a ISA-494 Service Air to Train "A" 2165-S-998 S02 F-3 6140 I GL SO 3 B Act 0 C C FSC Q n/a Chilled Water Expansion PIT 2YR n/a Tank STC Q n/a ISA-495 Service Air to Train "A" 2165-S-998 S02 F-4 6140 I GL SO 3 B Act 0 C C FSC Q n/a Chilled Water Expansion PIT 2YR n/a Tank STC Q n/a ISA-502 Service Air to Train "B" 2165-S-999 S02 F-3 6140 I GL SO 3 B Act 0 C C FSC Q n/a Chilled Water Expansion PIT 2YR n/a Tank STC Q n/a ISA-503 Service Air to Train "B" 2165-S-999 S02 F-3 6140 I GL SO 3 B Act 0 C C FSC Q n/a Chilled Water Expansion PIT 2YR n/a Tank STC Q

~

n/a ISA-80 Service Air to Containment 2165-S-800 C2 6140 2 GL MAN 2 A Pass LC C n/a LJ 2YR n/a (CIV)

ISA-82 Service Air to Containment 2165-S-800 C-3 6140 2 CK SA 2 A/C Act C C n/a LJ 2YR n/a (CIV) SC RO SA-ROJ I IS C-20 Screen Wash to Main 2165-S-808 D-16 4115 3 GL EH 3 B Act 0/C 0/C C FSC Q n/a Reservoir Bay 8 Supply Iso PIT 2YR n/a Vlv. STC Q n/a STO Q n/a Revision 0 Page 63 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table r

Valve Nomenclature Flow Diagram

'Dw S stem, Size Body, Actuator',SafetyIOM Act/I Norm!Safety', Fail Test Test CSJ/ROJ Number ;Coord (inch) Class Cat I Pass'os Pos '.

Pos Type Freq RR ISC-30 Screen Wash to Main 2165-S-808 D-13 4115 3 GL EH 3 B Act 0/C 0/C C FSC Q n/a Reservoir Bay 6 Supply Iso PIT 2YR n/a Vlv. STC Q n/a STO Q n/a ISC-37 Screen Wash to Auxiliary 2165-S-808 B-13 4115 3 GL EH 3 B Act 0/C 0/C C FSC Q n/a Reservoir Bay 6 Supply Iso PIT 2YR n/a Vlv. STC Q n/a STO Q n/a ISC-40 Screen Wash to Auxiliary 2165-S-808 B-16 4115 3 GL EH 3 B Act 0/C 0/C C FSC Q n/a Reservoir Bay 8 Supply Iso PIT 2YR n/a Vlv. STC Q n/a STO Q n/a ISF-118 FPCS Purif Pump Suction 2165-S-561 E-2 7110 4 DA MAN 2 A Pass LC C n/a LJ 2YR n/a from Refueling Cavity (CIV)

I SF-119 FPCS Purif Pump Suction 2165-S-561 E-3 7110 4 DA MAN 2 A Pass LC C n/a LJ 2YR n/a from Refueling Cavity (CIV)

I SF-13 FPC Pump "I & 4B-SB" 2165-S-805 J-9 7110 12 CK SA 3 C Act 0/C 0 n/a SO n/a Discharge Check Vlv ISF-144 FPCS Purif Pump Return to 2165-S-561 A-3 7110 4 DA MAN 2 A Pass LC C n/a LJ 2YR n/a Refueling Cavity (CIV)

ISF-145 FPCS Purif Pump Return to 2165-S-561 A-2 7110 4 DA MAN 2 A Pass LC C n/a LJ 2YR n/a Refueling Cavity (CIV)

ISF-3 FPC Pump "I & 4A-SA" 2165-S-805 G-9 7110 12 CK SA 3 C Act 0/C 0 n/a 'O n/a Discharge Check Vlv ISF-45 Fuel Pool Hx "I & 4A-SA" 2165-S-805 H-3 7110 .75X I RV SA 3 C Act C 0/C n/a SP 10YR n/a Relief Vlv ISF-66 Fuel Pool Hx "I & 4B-SB" 2165-S-805 K-3 7110 .75X I RV SA 3 C Act C 0/C n/a SP IOYR n/a Relief Vlv Revision 0 Page 64 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Body Actu t ~safetyloMIAct/,'NormiSafety Valve g System Fail Test Test CSJ/ROJ Number Nomenclature Flow Diagram ~i

,Coord

~

I i

(inch)

I

'lass Cat Pass 'os l Pos Pos Type Freq RR 1SI-1 Boron Injection Tank (BIT) 2165-S-1308 M-5 2080 3 GA MO 2 B Act C 0 Al PIT 2YR n/a Inlet Iso Vlv STO Q n/a 1SI-10 RCS Cold Leg Loop 3 Inj 2165-S-1308 E-5 2080 2 CK SA I C Act C 0/C n/a SC RO SI-ROJ I Ck Vlv (CIV) SO RO SI-ROJ I ISI-104 RCS Hot Leg Loop I Inj Ck 2165-S-1308 E-12 2080 2 CK SA I C Act C 0/C n/a SC RO SI-ROJ I Vlv (CIV) SO RO SI-ROJ I ISI-105 RCS Hot Leg Loop 21nj Ck 2165-S-1308 E-13 2080 2 CK SA I C Act C 0/C n/a SC RO SI-ROJ I Vlv (CIV) SO RO SI-ROJ I ISI-106 RCS Hot Leg Loop 3 Inj Ck 2165-S-1308 E-14 2080 2 CK SA I C Act C 0/C n/a SC RO SI-ROJ I Vlv (CIV) SO RO SI-ROJ I ISI-107 Alternate High Head SI to 2165-S-1308 H-15 2080 3 GA MO 2 B Act C 0/C AI PIT 2YR n/a Hot Leg (CIV) STC RO SI-ROJ2 STO RO SI-ROJ2 1SI-127 RCS Hot Leg Loop I Inj Ck 2165-S-1308 E-15 2080 2 CK SA I C Act C 0/C n/a SC RO SI-ROJ I Vlv (CIV) SO RO SI-ROJ I ISI-128 RCS Hot Leg Loop 2 Inj Ck 2165-S-1308 E-16 2080 2 CK SA I C Act C 0/C n/a SC RO SI-ROJ I Vlv (CIV) SO RO SI-ROJ I ISI-129 RCS Hot Leg Loop 3 Injn 2165-S-1308 E-17 2080 2 CK SA I C Act C 0/C n/a SC RO SI-ROJ I Ck Vlv (CIV) SO RO SI-ROJ I ISI-134 Sl Low Head to RCS Hot 2165-S-1308 B- I I 2080 6 CK SA I A/C Act C 0/C n/a LK 2YR n/a Leg Loops I (CIV) (PIV) SC RO SI-ROJ5 SO CS SI-CSJ I ISI-135 Sl Low Head to RCS Hot 2165-S-1308 C- I I 2080 6 CK SA I A/C Act C 0/C n/a LK 2YR n/a Leg Loop 2 (CIV) (PIV) SC RO SI-ROJ5 SO CS SI-CSJ I ISI-136 RCS Hot Leg Loop I Inj Ck 2165-S-1308 B-17 2080 6 CK SA I C Act C 0/C n/a SC RO SI-ROJ5 Vlv SO CS SI-CSJ I ISI-137 RCS Hot Leg Loop 2 Inj Ck 2165-S-1308 C-17 2080 6 CK SA I C Act C 0/C n/a SC RO SI-ROJ5 Vlv SO CS SI-CSJ I Revision 0 Page 65 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table l'=

Valve g ','ody OM Act/'orm Safety Fail Test Test CSJ/ROJ Number Nomenclature Flow Diagram I ~~

System l Actuator'165-S-1308 Cat Pass I I Pos, Pos 'os Type Freq RR ISI-138 RCS Hot Leg Loop 3 Inj Ck D-17 2080 6 CK SA I C Act C OlC n/a SC RO S I-ROJ I Vlv SO RO SI-ROJ I ISI-179 Accumulator Fill from 2165-S-1309 J-17 2090 I GL AO 2 A Act 0/C C C FSC Q n/a RWST (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a I SI-182 Accumulator Fill from 2165-S-1309 J-16 2090 I CK SA 2 A/C Act 0/C 0/C n/a LJ 2YR n/a RWST (CIV) SC RO SI-ROJ3 SO CS SI-CSJ3 ISI-186 Accumulator "A" Fill from 2165-S-1309 D-13 2090 I GL AO 2 B Pass C C C PIT 2YR n/a RWST ISI-187 Accumulator "B" Fill from 2165-S-1309 G-13 2090 I GL AO 2 B Pass C C C PIT 2YR n/a RWST ISI-188 Accumulator "C" Fill from 2165-S-1309 K-13 2090 I GL AO 2 B Pass C C PIT 2YR n/a RWST ISI-2 Boron Injection Tank (BIT) 2165-S-1308 N-5 2080 3 GA MO 2 B Act C 0 AI PIT Q n/a Inlet Iso Vlv STO Q n/a ISI-225 Sl Accumulator "A" 2165-S-1309 B-12 2090 RV SA 2 C Act O/C n/a SP IOYR n/a Pressure Relief Vlv ISI-226 SI Accumulator "B" 2165-S-1309 E-12 2090 RV SA 2 C Act C OIC n/a SP IOYR n/a Pressure Relief Vlv ISI-227 Sl Accumulator "C" 2165-S-1309 1-12 2090 I RV SA 2 C Act C 0/C n/a SP IOYR n/a Pressure Relief Vlv ISI-246 SI Accumulator "A" 2165-S-1309 D-10 2090 12 GA MO 2 B Pass 0 0 Al PIT 2YR n/a Discharge Iso Vlv ISI-247 Sl Accumulator "B" 2165-S-1309 G- I 0 2090 12 GA MO 2 B Pass 0 0 Al PIT 2YR n/a Discharge Iso Vlv IS1-248 Sl Accumulator "C" 2165-S-1309 K-10 2090 12 GA MO 2 B Pass 0 0 Al PIT 2YR n/a Discharge Iso Vlv Revision 0 Page 66 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table

'Dwg t Valve Nomenclature Flow Diagram "

System Size Actuator Safety OM Act /, Norm 'Safety, Bod iActuator, Body ~l, Fail Test Test CSJ/ROJ Number I

(

Coordi (inch)

I Class Cat lPass Pos 'Pos

, Pos 'ype Freq RR ISI-249 SI Accumulator "A" 2165-S-1309 D-6 2090 12 CK SA I A/C Act C 0/C n/a LK 2YR n/a Discharge Check Vlv (PIV) PSO RO Sl-VR I SDIS RO Sl-VR I ISI-250 Sl Accumulator "A" 2165-S-1309 D-3 2090 12 CK SA I A/C Act C 0/C n/a LK 2YR n/a Discharge Check Vlv (PIV) PSO RO Sl-VR I SDIS RO Sl-VR I ISI-251 Sl Accumulator "B" 2165-S-1309 G-6 2090 12 CK SA I A/C Act C 0/C n/a LK 2YR n/a Discharge Check Vlv (PIV) PSO RO SI-VR I SDIS RO Sl-VR I I SI-252 Sl Accumulator "B" 2165-S-1309 G-3 2090 12 CK SA I A/C Act C 0/C n/a LK 2YR n/a Discharge Check Vlv (PIV) PSO RO Sl-VR I SDIS RO Sl-VR I ISI-253 Sl Accumulator "C" 2165-S-1309 J-6 2090 12 CK SA I A/C Act C 0/C n/a LK 2YR n/a Discharge Check Vlv (PIV) PSO RO Sl-VR I SDIS RO SI-VR I ISI-254 Sl Accumulator "C" 2165-S-1309 J-3 2090 12 CK SA I A/C Act C 0/C n/a LK 2YR n/a Discharge Check Vlv (PIV) PSO RO Sl-VR 1 SDIS RO SI-VR I 1SI-255 Accumulator "A" Check 2165-S-1309 E-7 2090 0.75 GL AO 2 B Pass C C C PIT 2YR n/a Vlv Test Line Iso Vlv ISI-256 Accumulator "A" Check 2165-S-1309 E-6 2090 0.75 GL AO 2 B Pass C C PIT 2YR n/a Vlv Test Line Iso Vlv ISI-257 Accumulator "B" Check 2165-S-1309 H-7 2090 0.75 GL AO 2 B Pass C C PIT 2YR n/a Vlv Test Line Iso Vlv ISI-258 Accumulator "B" Check 2165-S-1309 H-6 2090 0.75 GL AO 2 B Pass C C PIT 2YR n/a Vlv Test Line Iso Vlv ISI-259 Accumulator "C" Check 2165-S-1309 K-7 2090 0.75 GL AO 2 B Pass C C C PIT 2YR n/a Vlv Test Line Iso Vlv ISI-260 Accumulator "C" Check 2165-S-1309 K-6 2090 0.75 GL AO 2 B Pass C C C PIT 2YR n/a Vlv Test Line Iso Vlv Revision 0 Page67 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve Nomenclature Flow Diagram i, Dwg, S I '.

Size Bod ~Actuat .Safety) 0M lAct /: Norm Fail , Test Test CSJ/ROJ Number I' "Class I Cat Pass l

Pos,'os

',,Safety,'CoordI,(inch)

JI Pos  ; Type Freq RR ISI-263 Accumulator Check Vlv 2165-S-1309 D-5 2090 0.75 GL AO 2 A Act 0/C C C FSC Q n/a Test Return to RWST (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a I SI-264 Accumulator Check Vlv 2165-S-1309 D-4 2090 0.75 GL AO 2 A Act 0/C C C FSC Q n/a Test Return to RWST (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a ISI-287 Accumulators & Prz PORV 2165-S-1309 B-18 2090 I GL AO 2 A Act 0/C C C FSC Q n/a N2 Supply Iso Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a ISI-290 Accumulators & Prz PORV 2165-S-1309 B-17 2090 I CK SA 2 A/C Act 0/C C n/a LJ 2YR n/a N2 Supply Check Vlv (CIV) SC RO SI-ROJ3 ISI-295 Accumulator "A"N2 2165-S-1309 C- I I 2090 I GL AO 2 B Pass C C C PIT 2YR n/a Supply and Vent ISI-296 Accumulator "B" N2 2165-S-1309 E-11 2090 I GL AO 2 B Pass C C C PIT 2YR n/a Supply and Vent ISI-297 Accumulator "C" N2 2165-S-1309 1-11 2090 I GL AO 2 B Pass C C PIT 2YR n/a Supply and Vent ISI-3 Boron Injection Tank (BIT) 2165-S-1308 I 2 2080 3 GA MO 2 B Act C 0/C Al PIT 2YR n/a Outlet Iso Vlv (CIV) STC Q n/a STO Q n/a ISI-300 Containment Sump to RHR 2165-S-1310 N-6 2080 14 GA MO 2 B Act C 0/C AI PIT 2YR n/a Pump "A" Iso Vlv (CIV) STC Q n/a STO Q n/a ISI-301 Containment Sump to RHR 2165-S-1310 M-6 2080 14 GA MO 2 B Act C 0/C Al PIT 2YR n/a Pump "B" Iso Vlv (CIV) STC Q n/a STO Q n/a ISI-310 Containment Sump to RHR 2165-S-1310 N-7 2080 14 GA MO 2 B Act C 0/C Al PIT 2YR n/a Pump "A" Iso Vlv STO Q n/a Revision 0 Page68 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve Number Nomenclature Flow Diagram Coord Size (inch)

B d A, Safety'M Act /'orm 'afety, Fail I

Class Cat Pass I Pos Pos Pos Test Test Type Freq CSJ/ROJ RR ISI-311 Containment Sump to RHR 2165-S-1310 M-7 2080 14 GA MO 2 A Act C 0/C Al PIT 2YR n/a Pump "B" Iso Vlv STO Q n/a ISI-320 RHR Pump "A" Suction 2165-S-1310 N-12 2080 14 CK SA 2 C Act C 0/C n/a SC RO SI-RO34 Supply Check Vlv. from SO Q n/a RWST ISI-321 RHR Pump "B" Suction 2165-S-1310 M-12 2080 14 CK SA 2 C Act C 0/C n/a SC RO SI-RO/4 Supply Check Vlv. from SO Q n/a RWST 1SI-322 RHR Pump "A" Suction 2165-S-1310 N-10 2080 14 GA MO 2 B Act 0 OIC AI PIT 2YR n/a Supply Iso Vlv. from RWST STC Q n/a STO Q n/a ISI-323 RHR Pump "B" Suction 2165-S-1310 M-10 2080 14 GA MO 2 B Act 0 0/C Al PIT 2YR n/a Supply Iso Vlv. from RWST STC Q n/a STO Q n/a ISI-326 Low Head Sl Train "A" to 2165-S-1310 D-6 2080 10 GA MO 2 B Act 0 0/C AI PIT 2YR n/a Hot Leg Crossover STC Q n/a STO Q n/a 1 $ 1-327 Low Head Sl Train "A" to 2165-S-1310 E-6 2080 10 GA MO 2 B Act 0 0/C Al PIT 2YR n/a Hot Leg Crossover STC Q n/a STO Q n/a ISI-328 LHSI Header "A" Relief Vlv 2165-S-1310 B-4 2080 0.75 RV SA 2 C Act C 0/C n/a SP IOYR n/a ISI-329 LHSI Header "B" Relief Vlv 2165-S-1310 E-4 2080 0.75 RV SA 2 C Act C O/C n/a SP IOYR n/a ISI-330 RHR to Hot Leg Relief Vlv 2165-S-1310 B-5 2080 0.75 RV SA 2 C Act C 0/C n/a SP IOYR n/a ISI-340 LHSI Train "A"to Cold 2165-S-1310 C-4 2080 10 GA MO 2 A Act 0 0/C Al PIT 2YR n/a Legs (CIV) STC Q n/a STO Q n/a ISI-341 LHSI Train "8" to Cold 2165-S-1310 E-4 2080 10 GA MO 2 A Act 0 0/C Al PIT 2YR n/a Legs(CIV) STC Q n/a STO Q n/a Revision 0 Page69 of 145

HNP-IST-002

. HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve Flow Diagram; ' Body "Actuator'Safetyl OM IAct Norm Safety

/~ I Fail Test " Test CSJ/ROJ Number Nomenclature

'Coord",

System (inch) 'lass', Cat Pass Pos, Pos i Pos Type Freq RR ISI-346 LHSI Train "A" to Cold 2165-S-1310 C-3 2080 10 CK SA 2 A/C Act C 0/C n/a LK 2YR n/a Legs Inj. Check (PIV/CIV) SC RO Sl-ROJ5 SO CS SI-CSJ I IS 1-347 LHSI Train "B" to Cold 2165-S-1310 E-3 2080 10 CK SA 2 A/C Act C 0/C n/a LK 2YR n/a Legs Inj. Check (PIV/CIV) SC RO SI-ROJ5 SO CS SI-CSJ I 1SI-356 LHSI to RCS Cold Leg 2165-S-1310 C-2 2080 6 CK SA I A/C Act C 0/C n/a LK 2YR n/a Loop I (PIV) SC RO SI-ROJ5 SO CS SI-CSJ I 1SI-357 LHSI to RCS Cold Leg 2165-S-1310 E-2 2080 6 CK SA I A/C Act C 0/C n/a LK 2YR n/a Loop 2 (PIV) SC RO SI-ROJ5 SO CS SI-CSJ I ISI-358 LHSI to RCS Cold Leg 2165-S-1310 E-2 2080 CK SA I A/C Act. C 0/C n/a LK 2YR n/a Loop 3 (PIV) SC RO SI-ROJ5 SO CS SI-CSJ I 1SI-359 LHSI Trains "A" and "B" to 2165-S-1310 B-4 2080 10 GA MO 2 A Act C 0/C AI LK 2YR n/a RCS Hot Legs Loops I and PIT 2YR n/a 2 (CI V) (PI V) STC CS SI-CSJ2 STO CS SI-CSJ2 ISI-379 Hot Leg Check Vlv Test 2165-S-1308 B-11 2080 0.75 GL AO 2 B Pass C C C PIT 2YR n/a Line Iso Vlv ISI-380 Hot Leg Check Vlv Test 2165-S-1308 A-17 2080 0.75 GL AO 2 B Pass C C C PIT 2YR n/a Line Iso Vlv ISI-381 Cold Leg Check Vlv Test 2165-S-1308 A-7 2080 0.75 GL AO 2 B Pass C C C PIT 2YR n/a Line Iso Vlv 1SI-382 Cold Leg Check Vlv Test 2165-S-1308 B-8 2080 0.75 GL AO 2 B Pass C C C PIT 2YR n/a Line Iso Vlv 1SI-383 Cold Leg Check Vlv Test 2165-S-1308 C-8 2080 0.75 GL AO 2 B Pass C C C PIT 2YR n/a Line Iso Vlv ISI-384 Accumulator "A" Cold Leg 2165-S-1309 E-6 2090 0.75 GL AO 2 B Pass C C C PIT 2YR n/a Check Vlv Test Line Iso Vlv Revision 0 Page70 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table f

Valve Nomenclature Flow Diagram "g System Bod Actuator'Safety, OM IAct / Norm I Safety . Fail Test Test CSJ/ROJ Number I

,Coord; I

(inch) 'lass" Cat" Pass Pos Pos i Pos Type Freq RR ISI-385 Accumulator "B" Cold Leg 2165-S-1309 1-6 2090 0.75 GL AO 2 B Pass C C C PIT 2YR n/a Check Vlv Test Line Iso Vlv ISI-386 Accumulator "C" Cold Leg 2165-S-1309 L-6 2090 0.75 GL AO 2 B Pass C C C PIT 2YR n/a Check Vlv Test Line Iso Vlv ISI-387 Hot Leg Check Vlv Test 2165-S-1310 A-2 2080 0.75 GL AO 2 B Pass C C C PIT 2YR n/a Line Iso Vlv (CIV)

ISI-388 Cold Leg Check Vlv Test 2165-S-1310 D-2 2080 0.75 GL AO 2 B Pass C C C PIT 2YR n/a Line Iso Vlv (CIV) 1SI-389 Cold Leg Check Vlv Test 2165-S-1310 B-2 2080 0.75 GL AO 2 B Pass C C C PIT 2YR n/a Line Iso Vlv ISI-390 Cold Leg Check Vlv Test 2165-S-1310 C-2 2080 0.75 GL AO 2 B Pass C C PIT 2YR Line Iso Vlv ISI-391 Cold Leg Check Vlv Test 2165-S-1310 F-2 2080 0.75 GL AO 2 B Pass C PIT 2YR n/a Line Iso Vlv (CIV)

ISI-4 Boron Injection Tank (BIT) 2165-S-1308 1-3 2080 3 GA MO 2 B Act C 0/C AI PIT 2YR n/a Outlet Iso Vlv (CIV) STC Q n/a STO Q n/a ISI-444 Instr. Air Inlet Check Vlv to 2165-S-1309 B-6 2050 I CK SA 3 A/C Act 0/C C n/a LK 2YR n/a PORV N2/Air Accum. Tank SC RO RC-ROJ2 IA-SA ISI-446 Instr. Air Inlet Check Vlv to 2165-S-1309 A-6 2050 I CK SA 3 A/C Act 0/C C LK 2YR n/a PORV N2/Air Accum. Tank SC RO RC-ROJ2 IC-SB ISI-52 Alternate High Head Sl to 2165-S-1308 H-10 2080 3 GA MO 2 B Act C 0/C AI PIT 2YR n/a Cold Leg (CIV) STC RO SI-ROJ2 STO RO SI-ROJ2 ISI-72 RCS Cold Leg Loop I Alt. 2165-S-1308 E-6 2080 2 CK SA I C Act C 0/C n/a SC RO SI-ROJ I Inj Ck Vlv (CIV) SO RO SI-ROJ I ISI-73 RCS Cold Leg Loop 2 Alt. 2165-S-1308 E-7 2080 2 CK SA I C Act C 0/C n/a SC RO SI-ROJ I Inj Ck Vlv (CIV) SO RO SI-ROJ I Revision 0 Page71 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table I

Valve Nomenclature Flow Diagram wg System Bod Act 'Safety OM Act/ Norm ISafety Fail 'est Test CSJ/ROJ Number ll,

,Coordj (inch) . Class Cat Pass, Pos J

Pos Pos 'ype Freq RR ISI-74 RCS Cold Leg Loop 3 Alt. 2165-S-1308 E-8 2080 2 CK SA I C Act C 0/C n/a SC RO SI-ROJ I Inj Ck Vlv (CIV) SO RO SI-ROJ I ISI-8 RCS Cold Leg Loop I Inj 2165-S-1308 E-3 2080 2 CK SA I C Act C 0/C n/a SC RO SI-ROJ I Ck Vlv (CIV) SO RO SI-ROJ I ISI-81 RCS Cold Leg Loop I 2165-S-1308 B-3 2080 6 CK SA I C Act C 0/C n/a SC RO SI-ROJ5 injection Check SO CS SI-CSJ I ISI-82 RCS Cold Leg Loop 2 2165-S-1308 C-3 2080 6 CK SA I C Act C 0/C n/a SC RO SI-ROJ5 Injection Check SO CS SI-CSJ I ISI-83 RCS Cold Leg Loop 3 2165-S-1308 D-3 2080 6 CK SA I C Act C 0/C n/a SC RO SI-ROJ5 Injection Check SO CS SI-CSJ I ISI-86 High Head Sl to Hot Leg 2165-S-1308 H-12 2080 3 GA MO 2 B Act C 0/C Al PIT 2YR n/a (CIV) STC RO SI-ROJ2 STO RO SI-ROJ2 ISI-9 RCS Cold Leg Loop 2 Inj 2165-S-1308 E-4 2080 2 CK SA I C Act C 0/C SC RO SI-ROJ I Ck Vlv (CIV) SO RO SI-ROJ I ISP-12 Hydrogen Analyzer Cabinet 2165-S-605 C-12 2075 I GL SO 2 A Act 0 0/C FSC Q n/a "IA"Supply Iso Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a STO Q n/a ISP-16 REM-3502A Inlet from 2165-S-605 F-12 7005 I GL SO 2 A Act 0 C FSC Q n/a Containment Atmosphere LJ 2YR n/a Iso Vlv (CIV) PIT 2YR n/a STC Q n/a ISP-200 PASS Liquid Return Hdr 2165-S-552 N-6 2117 I GL SO 2 A Act 0/C C FSC Q n/a Iso Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a Revision 0 Page 72 of 145

0 0

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Nomenclature Flow Diagram System Size Bod )A Safety OM Act/ Norm )Safety Fail ~

Test Test" C SJ/ROJ j

Number Coord (inch) Class Cat Pass Pos Pos Pos ~ Type Freq RR

)

1SP-201 PASS Liquid Return Hdr 2165-S-552 N-5 2117 I GL SO 2 A Act 0/C C C FSC n/a Iso Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a ISP-208 PASS Gas Return Hdr Iso 2165-S-552 N-6 2117 0.75 GL SO 2 A Act 0/C C C FSC Q n/a Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a IS P-209 PASS Gas Return Hdr Iso 2165-S-552 N-5 2117 0.75 GL SO 2 A Act 0/C C C FSC Q n/a Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a ISP-214 SG "A" Shell Outlet to 2165-S-551 C-5 3100 0.75 GA AO 2 8 Act 0/C C C FSC Q n/a Sample Panel Iso Vlv PIT 2YR n/a STC Q n/a 1SP-216 SG "A" Tube Outlet to 2165-S-551 D-5 3100 0.75 GA AO 2 8 Act 0/C C C FSC Q n/a Sample Panel Iso Vlv PIT 2YR n/a STC Q n/a 1SP-217 SG "A" to Sample Panel Iso 2165-S-551 C-6 3100 0.75 GL SO 2 8 Act 0/C C C FSC Q n/a Vlv (CIV) PIT 2YR n/a STC Q n/a 1SP-219 SG "8" Shell Outlet to 2165-S-551 H-5 3100 0.75 GA AO 2 8 Act 0/C C C FSC Q n/a Sample Panel Iso Vlv PIT 2YR n/a STC Q n/a ISP-221 SG "8" Tube Outlet to 2165-S-551 1-5 3100 0.75 GA AO 2 8 Act 0/C C C FSC Q n/a Sample Panel Iso Vlv PIT 2YR n/a STC Q n/a 1SP-222 SG "8" to Sample Panel Iso 2165-S-551 H-6 3100 0.75 GL SO 2 8 Act 0/C C C FSC Q n/a Vlv (CIV) PIT 2YR n/a STC Q n/a Revision 0 Page73 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Nomenclature Flow Diagram, ' System

'ize Body Actuato ISafety OM}Act/INorm Safety'~ Fail; Test Test CSJ/ROJ Number Coord ,(inch) Class Cat jPass j Pos Pos Pos Type Freq RR

} ,

ISP-224 SG "C" Shell Outlet to 2'165-S-551 L-5 3100 0.75 GA AO 2 B Act 0/C C C FSC Q n/a Sample Panel Iso Vlv PIT 2YR n/a STC Q n/a ISP-226 SG "C" Tube Outlet to 2165-S-551 M-5 3100 0.75 GA AO 2 B Act 0/C C C FSC Q n/a Sample Panel Iso Vlv PIT 2YR n/a STC Q n/a ISP-227 SG "C" to Sample Panel Iso 2165-S-551 M-6 3100 0.75 GL SO 2 B Act 0/C C C FSC Q n/a Vlv (CIV) PIT 2YR n/a STC Q n/a 1SP-40 Pzr Liquid Space Sample 2165 S 552 C4 2115 0375 GL SO 2 A Act 0 C C FSC Q n/a Iso Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a 1SP-41 Pzr Liquid Space Sample 2165-S-552 C-5 2115 0.375 GL SO 2 A Act 0 C C FSC Q n/a Iso Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a ISP-42 Hydrogen Analyzer Cabinet 2165-S-605 G-12 2075 I GL SO 2 A Act C 0/C C FSC Q n/a "IB" Supply Iso Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a STO Q n/a 1SP-59 Pzr Steam Space Sample Iso 2165-S-552 D-4 2115 0.375 GL SO 2 A Act 0 C C FSC Q n/a Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a 1SP-60 Pzr Steam Space Sample Iso 2165-S-552 D-5 2115 0.375 GL SO 2 A Act 0 "

C C FSC Q n/a Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a Revision 0 Page74 of 145

0 HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve "g System [ Size iii d iA i i tSoferyiOMjAer/lworm I Safety Fail Test Test CSJ/ROJ Number Nomenclature Flow Diagram ICoordi I

I(inch) 'I . Class Cat Pass I Pos I ~

'os Pos t Type Freq RR ISP-62

'/C Hydrogen Analyzer Cabinet 2165-S-605 1-12 2075 I GL SO 2 A Act C. C FSC Q n/a "IB" Return Iso Vlv (CIV) LJ 2YR n/a PIT

'YR n/a STC Q n/a STO Q n/a ISP-78 SIS Accumulator "A" 2165-S-552 D-3 2115 0.375 GL SO 2 A Act 0/C C C FSC Q n/a Sample Iso Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a IS P-81 SIS Accumulator "B" 2165-S-552 E-3 2115 0.375 GL SO 2 A Act 0/C C FSC Q n/a Sample Iso Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a ISP-84 SIS Accumulator "C" 2165-S-552 F-3 2115 0.375 GL SO 2 A Act 0/C C FSC Q n/a Sample Iso Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a ISP-85 SIS Accumulator Sample 2165-S-552 E4 2115 0375 GL SO 2 A Act 0/C C C FSC Q n/a Iso Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a ISP-901 H2 Analyzer Cabinet "IA" 2165-S-605 A-9 2075 0.375 GL SO -

2 B Act C 0/C C FSC Q n/a Supply from Dome Iso Vlv PIT 2YR n/a STC Q n/a STO Q n/a ISP-902 H2 Analyzer Cabinet "IA" 2165-S-605 C-9 2075 0.375 GL SO 2 B Act C 0/C C FSC Q n/a Supply from RCP & SG PIT 2YR n/a "C" Iso Vlv STC n/a Q

STO Q n/a

. Revision 0 Page 75 of 145

Y'1 HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table I= lf 1

Valve Nomenclature Flow Diagram wg 'ystem : Size i Body.ActuatorisafetylOM;Act/l Norm I Safety,l Fail . Test Test, CSJ/ROJ Number ,Coord~ I(inch) ~

Class ',

Cat Pass

~j Pos i Pos Pos ',

Type. Freq RR i i ISP-903 H2 Analyzer Cabinet "IA" 2165-S-605 C-9 2075 0 375 GL SO 2 B Act C 0/C C FSC Q n/a Supply from RCP & SG PIT 2YR n/a "B" Iso Vlv STC n/a Q

STO n/a ISP-904 H2 Analyzer Cabinet "IA" 2165-S-605 8-9 2075 0.375 GL SO 2 B Act C 0/C C FSC Q n/a Supply from RCP & SG PIT 2YR n/a "A" Iso Vlv STC n/a Q

STO Q n/a ISP-905 H2 Analyzer Cabinet "IA" 2165-S-605 D-9 2075 0.375 GL SO 2 B Act C 0/C C FSC Q n/a Supply from Below Flux PIT 2YR n/a Mapping Rm Floor Iso Vlv STC Q n/a STO Q n/a ISP-906 H2 Analyzer Cabinet "IA" 2165-S-605 D-9 2075 0.375 GL SO 2 B Act 0 0/C C FSC Q n/a Supply from Pressurizer Iso PIT 2YR n/a Vlv STC Q n/a STO Q n/a ISP-907 H2 Analyzer Cabinet "I B" 2165-S-605 F-9 2075 0.375 GL SO 2 B Act C . 0/C C FSC Q n/a Supply from Dome Iso Vlv PIT 2YR n/a STC Q n/a STO Q n/a IS P-908 H2 Analyzer Cabinet "I B" 2165-S-605 G-9 2075 0.375 GL SO 2 B Act C 0/C C FSC Q n/a Supply from RCP & SG PIT 2YR n/a "C" Iso Vlv STC n/a Q

STO Q n/a ISP-909 H2 Analyzer Cabinet "I B" 2165-S-605 F-9 2075 0.375 GL SO 2 B Act C 0/C C FSC Q n/a Supply from RCP & SG PIT 2YR n/a "B" Iso Vlv STC n/a Q

STO Q n/a IS P-910 H2 Analyzer Cabinet "I B" 2165-S-605 F-9 2075 0.375 GL SO 2 B Act C 0/C C FSC Q n/a Supply from RCP & SG PIT 2YR n/a "A" Iso Vlv STC n/a Q

STO n/a Revision 0 Page76 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table W

Valve Nomenclature Flow Diagram, g, System Size B d A Safety'OM,Act/ Norm 'Safety, Fail Test Test CSJ/ROJ Number 'Coo rd', (inch) Class Cat Pass Pos Pos Pos Type Freq RR Jl W

ISP-911 -

H2 Analyzer Cabinet "I B" 2165-S-605 G-9 2075 0.375 GL SO 2 B Act C 0/C C FSC Q n/a Supply from Below Flux PIT 2YR n/a Mapping Rm Floor Iso Vlv STC Q n/a STO n/a ISP-912 H2 Analyzer Cabinet "I B" 2165-S-605 G-9 2075 0.375 GL SO B Act 0 0/C C FSC Q n/a Supply from Pressurizer Iso PIT 2YR n/a Vlv STC Q n/a STO Q n/a ISP-915 Hydrogen Analyzer Cabinet 2165-S-605 C-12 2075 GL SO 2 A Act 0 0/C C FSC Q n/a "IA"Supply Iso Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a STO Q n/a I SP-916 REM-3502A Inlet from 2165-S-605 F-12 7005 I GL SO 2 A Act 0 C C FSC Q n/a Containment Atmosphere LJ 2YR n/a Iso Vlv (CIV) PIT 2YR n/a STC Q n/a IS P-917 Hydrogen Analyzer Cabinet 2165-S-605 D-12 2075 I GL SO 2 A Act 0 0/C C FSC Q n/a "IA"Return Iso Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a STO Q n/a ISP-918 REM-3502A Sample 2165-S-605 F-12 7005 I GL SO 2 A Act 0 C C FSC Q n/a Return to Containment LJ 2YR n/a Atmosphere Iso Vlv (CIV) PIT 2YR n/a STC Q n/a ISP-919 Hydrogen Analyzer Cabinet 2165-S-605 G-12 2075 I GL SO 2 A Act C 0/C C FSC Q n/a "IB"Supply Iso Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a STO Q n/a Revision 0 Page77 of 145

HNP-IST-002 HNP IST Program Plan -2nd Interval 5.3 Valve Table Valve Dwg S stem. Size Body. Actuator SafetylOMlAct/- Norm, safety Fail Test Test CSJ/ROJ Number Nomenclature Flow Diagram

'Coord (inch), ~ .

Class> Cat j Pass

~

Pos 'os II Pos Type Freq RR ISP-939 REM-3502A Sample 2165-S-605 F-12 7005 I GL SO 2 A Act 0 C C FSC Q n/a Return to Containment LJ 2YR n/a Atmosphere Iso Vlv (CIV) PIT 2YR n/a STC n/a I SP-941 Hydrogen Analyzer Cabinet 2165-S-605 D-12 2075 I GL SO 2 A Act 0 O/C FSC Q n/a "IA"Return Iso Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a STO n/a ISP-943 Hydrogen Analyzer Cabinet 2165-S-605 1-12 2075 I GL SO 2 A Act C 0/C C FSC Q n/a "IB" Return Iso Vlv (CIV) LJ 2YR n/a PIT 2YR n/a STC n/a STO n/a ISP-948 RCS Sample Line Iso Vlv 2165-S-552 B-4 2117 0.375 GL SO 2 A Act 0 C C FSC Q n/a (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a IS P-949 RCS Sample Line Iso Vlv 2165-S-552 B-5 2117 0.375 GL SO 2 A Act 0 C C FSC Q n/a (CIV) LJ 2YR n/a PIT 2YR n/a STC Q n/a ISW-I Aux. Reservoir Supply to 2165-S-547 B-5 4065 30 BF MAN 3 B Act LO 0/C n/a PIT 2YR n/a ESW Header "A" Iso Vlv SC Q n/a SO Q n/a ISW-10 ESW Pump "B" Discharge 2165-S-547 D-3 4065 30 CK SA 3 C Act C 0/C n/a SC Q n/a Check Vlv SO Q n/a ISW-1055 SW Outlet from WC-2 A- 2165-S-998 S02 F-13 4085 10 BF EH 3 B Act T 0 0 FSO Q n/a SA Condenser FCV PIT 2YR n/a STO Q n/a Revision 0 Page 78 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve Nomenclature I'low Diagram I Dwg System '; I Size'Bod IActuatorISafetyIOMIAct /, Norm ISafety I Fail Test Test CSJ/ROJ Number ,Coo I(inch) I,

'lass Cat i Pass'. Pos jt i Pos Pos,"Type Freq II RR ISW-107 ESW from AH-2 Return D-12 4065 X1.2 RV SA 2 C Act C 0/C n/a SP IOYR n/a rd'165-S-547 Relief Vlv (ClV)

ISW-1078 Condenser Recircuation 2165-S-998 S02 B-8 4085 0.75 RV SA 3 C Act C 0/C n/a SP IOYR n/a Pump Train "A" Discharge Relief ISW-1079 Condenser Recirculation 2165-S-998 S02 C-8 4085 8 CK SA 3 C Act 0/C C n/a SC Q n/a Pump Train "A" Discharge Check Vlv ISW-108 ESW from AH-4 Return 2165-S-547 C-13 4065 X1.2 RV SA 2 C Act C 0/C n/a SP IOYR n/a Relief Vlv (CIV)

ISW-109 ESW from AH-2 Return Iso 2165-S-547 C-12 4065 8 BF MO 2 B Act 0 0/C AI PIT 2YR n/a Vlv (CIV) STC Q n/a ISW-110 ESW from AH-4 Return Iso 2165-S-547 C-13 4065 8 BF MO 2 B Act 0 0/C AI PIT 2YR n/a Vlv (CIV) STC Q n/a ISW-116 Contmt Fan CLR AH-2&3 2165-S-547 H-7 4065 14 BF AO 2 B Act 0 C C FSC Q n/a ESW Return Orifice Bypass PIT 2YR n/a Iso Vlv STC Q n/a ISW-1170 ESW/SW Makeup to Train 2165-S-998 S02 G 5 4065 I CK SA 3 C Act C 0 n/a SO Q n/a "A" ESCW Check Vlv ISW-1171 ESW/SW Makeup to Train 2165-S-998 S02 G-5 4085 I GL SO 3 B Act C 0/C C FSC Q n/a "A" ESCW Iso Vlv PIT 2YR n/a STC Q n/a STO Q n/a IS W-118 Contmt Fan CLR AH-I&4 2 I 65-S-547 G-l3 4065 14 BF AO 3 B Act 0 C C FSC Q n/a ESW Return Orifice Bypass PIT 2YR n/a Iso Vlv STC Q n/a ISW-1203 ESW/SW Makeup to Train 2165-S-999 S02 G-5 4065 I CK SA 3 C Act C 0 n/a SO Q n/a "B" ESCW Check Vlv Revision 0 Page 79 of 145

0 r

HNP-IST-002 5.3 ISW-1208 Valve Table Number I SW-1204 Nomenclature ESW/SW Makeup to Train "B" ESCW Iso Vlv SW Outlet from WC-2 B-FiaIr Diagram 2165-S-999 S02 2165-S-999 S02 f

G-5 F-13

< PSysirm 4085 4085 Size (inch) 10 Body Actuator GL BF SO EH Safety OM Class Cat Pass 3

3 B

B Act Act HNP IST Program Plan - 2nd Interval Act/ Norm Safety Pos C

T Pos 0/C 0

Fail Pos 0

C I Test i Test I Type 'req FSC PIT STC STO FSO Q

2YR Q

Q Q

'SJ/ROJ RR n/a n/a n/a n/a n/a SB Condenser FCV PIT 2YR n/a STO Q n/a IS W-121 ESW Header "A" Supply to 2165-S-547 1-8 4065 8 BF MO 3 B Act C 0 AI PIT 2YR n/a MDAFWP "IA-SA"Iso Vlv STO Q n/a ISW-123 ESW Header "A" Supply to 2165-S-547 J-8 4065 8 BF MO 3 - B Act C 0 Al PIT 2YR n/a MDAFWP "1A-SA" Iso Vlv STO Q n/a ISW-1231 Condenser Recircuation 2165-S-999 S02 B-8 4085 0.75 RV SA 3 C Act C 0/C n/a SP 10YR n/a Pump Train "B" Discharge Relief ISW-1232 Condenser Recirculation 2165-S-999 S02 C-8 4085 8 CK SA 3 C Act 0/C C n/a SC n/a Pump Train "B" Discharge Check Vlv ISW-124 ESW Header "A" Supply to 2165-S-547 1-8 4065 BF MO 3 B Act C 0/C AI PIT 2YR n/a TDAFWP "IX-SAB" Iso STO Q n/a Vlv ISW-126 ESW Header "A" Supply to 2165-S-547 1-9 4065 BF MO 3 B Act C 0/C Al PIT 2YR n/a TDAFWP "I X-SAB" Iso STO Q n/a Vlv ISSV-I27 ESW Header "B" Supply to 2165-S-547 1-9 4065 8 BF MO 3 B Act C 0/C AI PIT 2YR n/a TDAFWP "I X-SAB" Iso STO Q n/a Vlv ISW-129 ESW Header "B" Supply to 2165-S-547 1-9 4065 8 BF MO 3 B Act C 0/C Al PIT 2YR n/a TDAFWP "I X-SAB" Iso STO Q n/a Vlv ISW-130 ESW Header "B" Supply to 2165-S-547 I-9 4065 8 BF MO 3 B Act C 0 Al PIT 2YR n/a MDAFWP "I B-SB" Iso Vlv STO Q n/a Revision 0 Page80 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval

),

5.3 Valve Table

~ =

T Valve Nomenclature Flow Diagram Dwg System ( Size 'B d~A tu t,,Safety OMiAct/liNorm "Safety II i Fail Test Test CSJ/ROJ Number II ICoord [(inch) i Class~ Cat Pass, Pos i Pos I Pos Type Freq RR ISW-132 ESW Header "B" Supply to 2165-S-547 J-10 4065 8 BF MO 3 B Act C 0 AI PIT 2YR n/a MDAFWP "IB-SB" Iso Vlv STO Q n/a ISW-141 ESW HDR "A" to CSIP 2165-S-547 H-8 4065 1.5 CK SA 3 C Act 0 0 n/a SO Q n/a "IA" Oil CLR Check Vlv ISW-1494 Containment Penetration M- 2165-S-547 E-17 4060 .75 RV SA 2 A/C Act C 0/C n/a LJ 2YR n/a 91 Pressure Relief Valve SP IOYR n/a (CIV)

ISW-150 CSIP "IA"Oil CLR ESW 2165-S-547 F-8 4065 .75X I RV SA 3 C Act C 0/C n/a SP IOYR n/a Outlet Relief Vlv ISW-152 ESW HDR "A" to CSIP 2165-S-547 H-10 4065 I.S CK SA 3 C Act 0/C 0 n/a SO n/a "IC" Oil CLR Check Vlv ISW-154 ESW HDR "B" to CSIP 2165-S-547 H-10 4065 I.S CK SA 2 C Act 0/C 0 n/a SO n/a "IC" Oil CLR Check Vlv ISW-160 CSIP "IC" Oil CLR ESW 2165-S-547 F-9 4065 .75X I RV SA 3 C Act C 0/C n/a SP IOYR n/a Outlet Relief Vlv ISW-163 ESW HDR "B" to CSIP 2165-S-547 H-10 4065 1.5 CK SA 3 C Act 0/C 0 n/a SO n/a "IB" Oil CLR Check Vlv ISW-171 CSIP "I B" Oil CLR ESW 2165-S-547 F-10 4065 .75X I RV SA 3 C Act C 0/C n/a SP IOYR n/a Outlet Relief Vlv ISW-179 ESW Hdr "A" Supply to 2165-S-547 1-15 4065 4 GA AO 3 B Act C C C FSC Q n/a CVCS Chiller Condensers PIT 2YR n/a Iso Vlv STC Q n/a ISW-180 ESW Hdr "B" Supply to 2165-S-547 I- I 5 4065 4 GA AO 3 B Act C C C FSC Q n/a CVCS Chiller Condensers PIT 2YR n/a Iso Vlv STC Q n/a ISW-2 Aux. Reservoir Supply to 2165-S-547 B-4 4065 30 BF MAN 3 B Act LO 0/C n/a PIT 2YR n/a ESW Header "B" Iso Vlv SC Q n/a SO Q n/a ISW-20 ESW Strainer "IA" 2165-S-547 E I 4065 3 BA AO 3 B Act 0/C 0 0 FSO Q n/a Backwash Iso Vlv STO Q n/a Revision 0 Page S1 of 145

HNP-IST-002 HNP IST Program Plan -2nd Interval 5.3 Valve Table t 7:

I Valve Nomenclature w<; System ,Size IBody Actuator'SafetyI',OMiAct/, Norm ISafety Fail Test Test CSJ/ROJ L=-

Number ,(inch)," ~,'ClassICatIPassI Pos I

Pos Pos; Type Freq RR ESW Hdr "B" Return from

'Coord.'165-S-547 1SW-204 K-17 4065 4 GA AO 3 B Act C C C FSC Q n/a CVCS Chiller Condensers PIT 2YR n/a Iso Vlv STC Q n/a 1SW-206 ESW Hdr "A" Return from 2165-S-547 K-16 4065 4 GA AO 3 B Act C C C FSC Q n/a CVCS Chiller Condensers PIT 2YR n/a Iso Vlv STC Q n/a 1SW-220 SW Booster Pump "IB" 2165-S-547 F-14 4065 14 CK SA 3 C Act 0/C C n/a SC Q n/a Bypass Check Vlv ISW-225 ESW to AH-I Supply Iso 2165-S-547 D-14 4065 8 BF MO 2 B Act 0 0/C Al PIT 2YR n/a Vlv (CIV) STC Q n/a 1SW-227 ESW to AH-4 Supply Iso 2165-S-547 D-14 4065 8 BF MO 2 B Act 0 0/C Al PIT 2YR n/a Vlv (CIV) STC Q n/a 1SW-23 ESW Strainer ".I B" 2165-S-547 E-3 4065 3 BA AO 3 B Act 0/C 0 0 FSO Q n/a Backwash Iso Vlv STO Q n/a 1SW-231 SW Supply to Containment 2165-S-547 D-15 4060 12 BF AO 2 A Act 0 C FSC Q n/a Fan Coil Units Iso Vlv LJ 2YR n/a (CIV) PIT 2YR n/a 1SW-233 SW Supply to Containment Fan Coil Units Check Vlv 2165-S-547 C-15 4060 12 CK 'A A/C Act 0 0/C STC LJ SC Q

2YR RO n/a n/a SW-ROJ I (CIV) SO Q n/a 1SW-240 SW Return from 2165-S-547 D-17 4060 12 BF AO 2 A Act 0 C FSC Q n/a Containment Fan Coil Units LJ 2YR n/a Iso Vlv (CIV) PIT 2YR n/a STC Q n/a ISW-242 SW Return from 2165-S-547 F-17 4060 12 BF AO 2 A Act 0 C FSC Q n/a Containment Fan Coil Units LJ 2YR n/a Iso Vlv (CIV) PIT 2YR n/a STC Q n/a I SW-25 ESW Hdr "A" Strainer 2165-S-547 F-2 4065 30 BF MAN 3 B Pass 0 0 PIT 2YR n/a Outlet Iso Vlv Revision 0 Page S2 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5,3 Valve Table I

Valve Nomenclature Flow Diagram wg t System 'od lActu tSafetyt OM Act /", Norm I Safety Fail , Test Test CSJ/ROJ Number <Coord]

Class Cat Pass'os i t j Pos '(inch)I Pos Type Freq RR I II t t 4 1SW-257 ESW to CCW Htx "IB" 2165-S-547 1-13 4065 .75X I RV SA 3 C Act C 0/C n/a SP IOYR n/a Thermal Relief Vlv ISW-26 ESW Hdr "B" Strainer 2165-S-547 F-3 4065 30 BF MAN 3 B Pass 0 0 n/a PIT 2YR n/a Outlet Iso Vlv 1SW-270 ESW Hdr "A" Discharge to 2165-S-547 J- I 7 4065 30 BF MO 3 B Act C 0 AI PIT 2YR n/a Aux Reservoir Iso Vlv STO Q n/a 1SW-271 ESW Hdr "B" Discharge to 2165-S-547 1-17 4065 30 BF MO 3 B Act C 0 Al PIT 2YR n/a Aux Reservoir Iso Vlv STO Q n/a ISW-274 ESW Return Hdr "B" to 2165-S-547 L-16 4065 30 BF MO 3 B Act 0 C Al PIT 2YR n/a NSW Disch. Hdr Iso Vlv STC Q n/a IS W-275 ESW Return Hdr "A" to 2165-S-547 L-15 4065 30 BF MO 3 B Act 0 C Al PIT 2YR n/a NSW Disch. Hdr Iso Vlv STC Q n/a ISW-276 Common Disch to NSWS 2165-S-547 M-15 4065 36 BF MO 3 B Act 0 C Al PIT 2YR n/a Hdr Iso Vlv STC Q n/a ISW-3 Main Reservoir Supply to 2165-S-547 B I 4065 30 BF MAN 3 B Act LC 0/C n/a PIT 2YR n/a ESW Header "A" Iso Vlv SC n/a Q

SO Q n/a ISW-33 ESW Hdr. "A" Iso Vlv 2165-S-547 G-I 4065 30 BF MAN 3 B Pass 0 0 n/a PIT 2YR n/a 1SW-34 ESW Hdr. "B" Iso Vlv 2165-S-547 G-2 4065 30 BF MAN 3 B Pass 0 0 PIT 2YR n/a 1SW-39 NSW Supply to ESW 2165-S-547 1-1 4065 30 BF MO 3 B Act 0/C C Al PIT 2YR n/a Header "A" Iso Vlv STC n/a Q

ISW-4 Main Reservoir Supply to 2165-S-547 B-3 4065 30 BF MAN 3 B Act LC 0/C PIT 2YR n/a ESW Header "B" Iso Vlv SC Q n/a SO Q n/a ISW-40 NSW Supply to ESW 2165-S-547 1-2 4065 30 BF MO 3 B Act 0/C C AI PIT 2YR n/a Header "B" Iso Vlv STC Q 'n/a IS W-45 ESW Hdr "B" to Deleted 2165-S-547 H-3 4065 3 PL AO 3 B Pass LC C PIT 2YR n/a SSE Pump Iso Vlv ISW-47 ESW Hdr "A" to Deleted 2165-S-547 H-4 4065 3 PL AO 3 B Pass C C C PIT 2YR n/a SSE Pump Iso Vlv Revision 0 Page S3 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Valve Nomenclature Fl D Dwg S t Size B d A t

'. Safety" OM Act /, Norm: Safety 'ail Test Test CSJ/ROJ Number ;Coord I,

(inch) ., Class Cat Pass Pos Pos, Pos Type Freq RR IS W-60 ESW to CCW Htx "IA" 2165-S-547 1-6 4065 .75X I RV SA 3 C Act C 0/C n/a SP IOYR n/a Thermal Relief Vlv ISW-86 SW Booster Pump "IA" 2165-S-547 F-6 4065 14 CK SA 3 C Act 0/C C n/a SC n/a Bypass Check Vlv ISW-9 ESW Pump "A" Discharge 2165-S-547 D-2 4065 30 CK SA 3 C Act C 0/C n/a SC Q n/a Check Vlv SO Q n/a ISW-91 ESW to AH-2 Supply Iso 2165-S-547 D-6 4065 8 BF MO 2 B Act 0 0/C Al PIT 2YR n/a Vlv (CIV) STC Q n/a ISW-92 ESW to AH-3 Supply Iso 2165-S-547 D-7 4065 8 BF MO 2 B Act 0 0/C Al PIT 2YR n/a Vlv (CIV) STC Q n/a ISW-95 ESW from AH-3 Return 2165-S-547 D-8 4065 X 1.2 RV SA 2 C Act C 0/C n/a SP IOYR n/a Relief Vlv (CIV)

ISW-96 ESW from AH-I Return 2165-S-547 D-9 4065 X1.2 RV SA 2 C Act C 0/C n/a SP 10YR n/a Relief Vlv (CIV)

ISW-97 ESW from AH-3 Return Iso 2165-S-547 D-8 4065 8 BF MO 2 B Act 0 0/C AI PIT 2YR n/a Vlv (CIV) STC n/a ISW-98 ESW from AH-I Return Iso 2165-S-547 D-9 4065 8 BF MO 2 B Act 0 0/C Al PIT 2YR n/a Vlv (CIV) STC Q n/a 3AV-V3-SA-I Filter Train Inlet Check Vlv 2168-G-517 S03 E-14 8210 6 CK SA 3 C Act C 0 n/a SO Q n/a From RAB to Emergency Exhaust Fan A 3AV-V4-SB-I Filter Train Inlet Check Vlv 2168-G-517 S03 G-14 8210 6 CK SA 3 C Act C 0 n/a SO n/a From RAB to Emergency Exhaust Fan B 3SC-41 Fire Service Screen Wash to 2165-S-808 B-16 4115 3 GL EH 3 B Act 0/C C FSC Q n/a Bay 8 Supply Iso Vlv. PIT 2YR n/a STC Q n/a PDT-01CB- PDT-7680A I Outside 2166-B-431 DP38 n/a 8060 .75 EFC SA 2 C Act 0 0/C n/a PIT 2YR n/a 7680A ISA- Containment Pressure (CIV) SC RO CB-ROJ I CV Revision 0 Page84 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Interval 5.3 Valve Table Number Nomenclature I

Flow Diagram wg; System

,'Coordi, (inch);

Body:Actuatori I Class I Cat Pass i Norm tSafety Pos ! Pos Pos 1

Fail: Test '

Test

'Type" Frcq CSJ/ROJ RR I

PDT-01CB- PDT-7680A Outside 2166-B-431 DP38 n/a 8060 .75 EFC SA 2 C Act 0 0/C n/a PIT 2YR n/a 7680ASA-CV Containment Pressure (CIV) SC RO CB-ROJ I PDT-01CB- PDT-7680B I Outside 2166-B-431 DP38 n/a 8060 .75 EFC SA 2 C Act 0 0/C n/a PIT 2YR n/a 7680BISB- Containment Pressure (CIV) SC RO CB-ROJ I CV PDT-01CB- PDT-7680B Outside 2166-B-431 DP38 n/a 8060 .75 EFC SA 2 C Act 0 0/C n/a PIT 2YR n/a 7680BSB-CV Containment Pressure (CIV) SC RO CB-ROJ I PDT-01CP- PDT-01CP-7611S Excess 2166-B-431 DP39 n/a 8170 .75 EFC SA 2 C Act 0 0/C n/a PIT 2YR n/a 7611S-CV Flow Check Valve (CIV) SC RO CB-ROJ I Revision 0 Page 85 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.4 Valve Relief Requests CB-VRI Component Dwg Safety OM Normal Safety D escription Flow Diagram System Coord Class Cat. Position Position I CB-3 Train "A" Containment Vacuum Relief 2165-S-1017 G-16 8060 2 A/C C 0/C Vlv (CIV)

I CB-7 Train "B" Containment Vacuum Relief 2165-S-1017 H-16 8060 2 A/C C 0/C Vlv (CIV)

Code Test Requirements Within every 6 month period operability tests shall be performed unless historical data indicates a requirement for more frequent testing. (OM-I, Para. 1.3.4.3(a))

Basis for Relief These vacuum breaker check valves are self-actuated and are located inside the primary reactor containment. Due to their physical location, there is no practical means to verify the open and close capability and set pressure on a 6 month frequency as required by OM-I, Para 7.3.2.4(a). Relief from this requirement is requested since OM- I does not provide any provision to defer testing ifit is considered to be impractical.

These valves are 24" swing type check valves with no pressure or position sensing accessories. The valve disk is normally held in the closed position by the force of two springs mounted on the valve pivot shaA. At a predetermined set pressure, an equilibrium exists where the seal area times set pressure are equal to and balanced against the spring when the valve is closed. When a differential across the valve causes a torque about the shaft greater than that produced by these forces, the valve will open as long as this force remains greater than the closing force produced by the two springs. When the flow and differential pressure drops to the extent that they produce less torque than the two springs, the valve will close.

The only practical method to verify the open and close capability is to manually exercise the valve disk through a complete cycle. The Containment Vacuum Relief System is not provided with the means to actuate these valves to the open or closed position with flow. Since, these valves are normally seated by spring pressure, the only practical method to verify the setpoint of the valves is to use a calibrated spring scale to measure the force required to unseat the disk.

Each of these activities would require entry into primary containment at power which is impractical. Containment entries during operational modes I through 4 are undesirable from a personal safety standpoint due to the high radiation environment and the high ambient temperatures affecting work conditions. Additionally, entry into containment during power operation is administratively controlled by a plant procedure with requirements to perform pre-entry airborne radioactivity and air quality samples, implementation of heat stress controls, control of materials, radiological controls, a containment closeout inspection and a local leakage rate test of the applicable entry hatch seals.

Testing during non-planned cold shutdown periods is also impractical due to the requirement to enter containment and the need to build scaffolding to access the valves. Additionally, in order to complete the testing of the subject valves, test equipment to verify the opening setpoint must be installed and subsequently removed.

Alternate Test The subject valves shall be tested to verify their open and close capability and set pressure in accordance with the requirements of OM-I each refueling outage.

Approval Status NRC review and approval is pending. This relief request expires on 2/2/99 unless approved by the NRC.

Revision 0 Page S6 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Intcval 5.4 Valve Relief Requests CC-VRI Component Dwg Safety OM Normal Safety Description Flow Diagram System Coord Class Cat. Position Position I CC-306 CCW Return From Gross Failed Fuel 2165-S-1322 C-6 4080 3 C 0 C Detector I CC-307 CCW Return From Gross Failed Fuel 2165-S-1322 C-6 4080 3 C Detector Code Test Requirements Verify reverse flow closure capability nominally every 3 months per the requirements of OM-IO, Para. 4.3.2.

Basis for Relief It is impractical to verify a full-stroke closure exercise of the subject check valves during power operation, during cold shutdowns or refueling outages. These valves are 0.75 inch forged steel piston check valves. These valves are located in the return line from the gross failed fuel detector. During normal plant operation these valves are open to provide a flow path from the gross failed fuel detector cooler to the suction of the component cooling water pumps. In the event of a failure of the integrity of the non-safety related gross failed fuel detector cooler or associated components, two redundant components are provided on the inlet and return lines as required by the system design. The isolation function of the outlet line is performed by the active closure of ICC-306 and I CC-307.

Since the subject check valves are installed in series with no intermediate test connections to verify individual valve closure they cannot be tested with system flow under any plant conditions. It is not practical to verify the full-stroke closure of these valves utilizing non-intrusive diagnostic methods due to their size. Since the design of the system requires two valve isolation, and since it is not practical to test the pair of valves in accordance with the requirements of the Code, these valves shall be disassembled as described in section 4.1.1 of USNRC NUREG-1482 "Guidelines for Inser vice Testing at Nuclear Power Plants."

Alternate Test A full-stroke closure exercise of the subject valves will be verified by a sample disassembly and inspection program as outlined in NRC Staff Position 2 in USNRC Generic Letter 89-04 "Guidance On Developing Acceptable Inservice Testing Programs." The subject valves are of the same design (manufacturer, size, model number and materials of construction) and have the same service conditions including valve orientation and together consist of one group. One of the subject valves shall be disassembled each refueling outage. During valve disassembly, the valve internals will be visually inspected for worn or corroded parts, and the valve disk shall be manually exercised. If the disassembled valve is not capable of being full-stroke exercised or ifthere is binding or failure of the valve internals, the other valve in this group shall also be disassembled, inspected, and manually full-stroke exercised during the same refueling outage.

Approval Status The use of NRC Staff Position 2 in USNRC Generic Letter 89-04 is approved by the USNRC.

Revision 0 Page S7 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.4 Valve Relief Requests CC-VR2 Component Dwg S t Safety OM Normal Safety Description Flow Diagram System ID Coord Class Cat. Position Position I CC-216 CCW To RCP "A" Thermal Barrier Inlet 2165-S-1321 N-2 4080 3 C 0 C Check Vlv I CC-227 CCW To RCP "B" Thermal Barrier Inlet 2165-S-1321 N-5 4080 3 C 0 C Check Vlv ICC-238 CCW To RCP "C" Thermal Barrier Inlet 2165-S-1321 N-9 4080 3 C 0 C Check Vlv Code Test Requirements Verify reverse flow closure capability nominally every 3 months per the requirements of OM-IO, Para. 4.3.2.

Basis for Relief It is impractical to perform a full-stroke closure exercise of the subject check valves during power operations, cold shutdown and refueling outages. The subject check valves are located inside primary containment in the component cooling water (CCW) supply lines to the individual Reactor Coolant Pump (RCP) thermal barriers heat exchangers. These valves are not provided with external position indication.

One of the functions of the component cooling water system is to provide coolant to the three reactor coolant pump packages, each consisting of one upper bearing lube oil cooler, one lower bearing lube oil cooler and one thermal barrier cooler. The thermal barrier is located between the turning vane diffuser and the pump shaft. During normal operation the thermal barrier heat exchanger is passive. The cooling and lubrication requirements for the RCP bearing and shaft seal assembly are supplied by seal injection water from the chemical and volume control system. In accordance with plant procedures, CCW flow through the thermal barrier heat exchanger should be supplied at all times when RCS temperature exceeds 200'F. In the event of a loss of seal injection, reactor coolant system (RCS) water fiows up through the thermal barrier heat exchanger to supply the radial bearings and shaft seal with water. The RCS water is cooled by the CCW circulating through the heat exchanger. In the event of a failure of one the integrity of the thermal barrier heat exchangers, the RCS leakage is required to be isolated by the closure of ICC-251, ICC-252 and the subject supply line check valves.

Testing of the subject valves are not practical during power operation and cold shutdowns. The only possible methods available to verify valve closure are by providing an alternate pressurized water source downstream of the valve and establishing a differential pressure across the valve disk, or by disassembly. Both methods of would require entry into primary containment and draining significant sections of CCW piping. Testing during power operations is not practical since plant procedures require CCW flow to the thermal barrier heat exchanger at all times when RCS temperature exceeds 200'F. Testing during cold shutdowns is not practical since cooling water to the reactor coolant pump thermal barriers and motor bearings must be isolated to perfom the test. This would require all reactor coolant pumps to be stopped.

Alternate Test A full-stroke closure exercise of the subject valves will be verified by a sample disassembly and inspection program as outlined in NRC Staff Position 2 in USNRC Generic Letter 89-04 "Guidance On Developing Acceptable Inservice Testing Programs." The subject valves are of the same design (manufacturer, size, model number and materials of construction) and have the same service conditions including valve orientation and together consist of one group. One of the subject valves shall be disassembled each refueling outage. During valve disassembly, the valve internals will be visually inspected for worn or corroded parts, and the valve disk shall be manually exercised. Ifthe disassembled valve is not capable of being full-stroke exercised or ifthere is binding or failure of the valve internals, the other two valves in this group shall also be disassembled, inspected, and manually full-stroke exercised during the same refueling outage.

Approval Status The use of NRC Staff Position 2 in USNRC Generic Letter 89-04 is approved by the USNRC.

Revision 0 Page SS of 145

HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.4 Valve Relief Requests CE-VR1 Component Description Flow Diagram Dwg System Safety OM Normal Safety Coo rd Class Cat. Position Position ICE-36 CST to MDAFWP "A" Inlet Check Vlv 2165-S-545 H-7 3070 3 C C 0/C ICE-46 CST to MDAFWP "B" Inlet Check Vlv 2165-S-545 H-8 3070 3 C C 0/C ICE-56 CST to TDAFWP Inlet Check Vlv 2165-S-545 H-9 3070 3 C C 0/C Code Test Requirements Verify reverse flow closure capability nominally every 3 months per the requirements of OM-10, Para. 4.3.2.

Basis for Relief These valves are in the auxiliary feedwater pump suction line from the condensate storage tank. These valves are dual plate check valves constructed by the same manufacturer, utilizing the same materials and have the same service conditions. I CE-36 and ICE-46 are 6 inch valves. ICE-56 is an 8 inch valve. The dual plate check valve is designed to block flow in only one direction and operate as a result of differential pressure. Two half-disc spring loaded plates are used as closure members hinged on a central vertical single pin. A torsion spring is used to actuate the plates for positive closure.

The auxiliary feed water pumps have two sources of supply water. The conde'nsate storage tank (CST) provides chemically treated condensate water and is the preferred source of water. The emergency service water (ESW) system is the alternate source and because it is not chemically treated it would be used only in an extreme emergency. The motor driven and turbine driven auxiliary feedwater pumps normally take suction from the (CST) via the common supply line. The safety function of these valves is to close to direct supply ESW system water to the suction of the auxiliary feedwater pumps when the CST is depleted.

It is not practical to verify closure of the subject check valves during power operation or during cold shutdowns. In order to verify closure of the subject valves, the CST would have to be drained and untreated ESW water would have to be introduced to the suction of the auxiliary feed water pumps. The ESW supply to the auxiliary feedwater pumps is normally isolated by two isolation valves for each connection between the auxiliary feedwater and ESW system. This prevents inadvertent leakage contamination of the auxiliary feedwater by impurities in the service water. Introduction of untreated water to the auxiliary feedwater system could negatively affect secondary plant water chemistry and could eventually cause damage to plant equipment. The use of non-intrusive techniques to conclusively verify closure of the subject valves as a result of cessation of pump flow is not considered practical due to the dual plate design of these valves.

Alternate Test A full-stroke closure of the subject valves will be verified by a sample disassembly and inspection program as outlined in NRC Staff Position 2 in USNRC Generic Letter 89-04 "Guidance On Developing Acceptable Inservice Testing Programs."

The subject valves are of similar design (manufacturer, model number and materials of construction) and have the same service conditions including valve orientation. The only Position 2 criterion not met is the common size for all valves in the sampling group. ICE-36 and ICE-46 are 6 inch valves and ICE-56 is an 8 inch valve. As identified in the NRC safety evaluation/technical evaluation (page 38 dated April 27, 1988) of the HNP 1st Ten-Year Interval IST Program, "Since all other factors are identical for these valves, the reviewer feels that even with the size disparity, these valves should be allowed to be grouped together because any failure mechanism should be common for all three valves."

Since the failure mechanism should be common for all three valves, only one of the subject valves shall be disassembled each refueling outage. During valve disassembly, the valve internals will be visually inspected for worn or corroded parts, and the valve disk will be manually exercised. Ifthe disassembled valve is not capable of being full-stroke exercised or if there is binding or failure of the valve internals, the other two valves in this group will also be disassembled, inspected, and manually full-stroke exercised during the same refueling outage.

Approval Status NRC review and approval is pending. This relief request expires on 2/2/99 unless approved by the NRC.

Revision 0 Page 89 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.4 Valve Relief Requests CT-VRI Component vg Safety OM Normal Safety ID Description Flow Diagram Coord System S t

'lass Cat. Position Position 1CT-53 Containment Spray Pump "A" Disch to 2165-S-550 F-3 2070 2 A/C C 0/C Nozzles Check Vlv (CIV)

ICT-91 Containment Spray Pump "B" Disch to 2165-S-550 K-3 2070 2, A/C C 0/C Nozzles Check Vlv (CIV)

Code Test Requirements Verify forward flow operability nominally every 3 months per the requirements of OM-IO,Para. 4.3.2.

Basis for Relief It is not practical to perform a full or part-stroke open exercise test of the subject valves during power operations or during cold shutdowns. These valves are 8 inch stainless steel swing check valves. The subject valves are located inside the primary containment building in the containment spray pump discharge lines to the containment spray nozzles.

The primary purpose of the containment spray system is to remove heat and fission products from a post-accident containment atmosphere. The containment spray system consists of two independent and redundant loops each containing a spray pump, piping, valves, spray headers and spray valves. The operation of the containment spray system is automatically initiated by the containment spray actuation signal (CSAS) which occurs when a containment pressure (Hl-3) signal is reached. Upon receipt of the CSAS, the containment spray pumps are started and borated water from the refueling water storage tank (RWST) (injection phase) or the containment recirculation sumps (recirculation phase) is discharged into the containment through the containment spray headers.

The subject check valves are normally closed during plant operation. These valves have a safety function to open to allow containment spray system water to discharge to the containment spray nozzles. Since, the subject check valves are located downstream of the full flow recirculation line test circuit, the only way to verify full or part-stroke exercise these valves to the open position would be by injecting a large quantity of water into the containment utilizing the containment spray pumps. Spraying the containment cbuld result in extensive damage to plant equipment located inside containment during all modes of plant operation.

The only practical method available to verify full-stroke opening capability is by disassembly and manually exercising the valve disk. The use of non-intrusive techniques to conclusively verify opening of the subject valves would also require flowing large quantities of wate'r into the containment building which is impractical.

Alternate Test A full-stroke opening exercise of the subject valves will be verified by a sample disassembly and inspection program as outlined in NRC Staff Position 2 in USNRC Generic Letter 89-04 "Guidance On Developing Acceptable Inservice Testing Programs." The subject valves are of the same design (manufacturer, size, model number and materials of construction) and have the same service conditions including valve orientation and together consist of one group. One of the subject valves shall be disassembled each refueling outage. During valve disassembly, the valve internals will be visually inspected for worn or corroded parts, and the valve disk shall be manually exercised. Ifthe disassembled valve is not capable of being full-stroke exercised or ifthere is binding or failure of the valve internals, the other valve in this group shall also be disassembled, inspected, and manually full-stroke exercised during the same refueling outage.

AAer the disassembly of the subject valves, these valves will be local leakage rate tested in accordance with the requirements of 10 CFR 50, Appendix J.

Approval Status The use of NRC Staff Position 2 in USNRC Generic Letter 89-04 is approved by the USNRC.

Revision 0 Page 90 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.4 Valve Relief Requests IA-VR1 Component Dwg System Safety OM Normal Safety Description Flow Diagram S ID Coord Class Cat. Position Position I IA-786 Instrument Air Supply Check to Accum. 2165-S-1017 G-13 6135 2 C 0/C C Tk. 1A-SA (Series with I IA-787) 1IA-787 Instrument Air Supply Check to Accum. 2165-S-1017 G-3 6135 2 C 0/C C Tk. 1A-SA (Series with I IA-786) 1IA-788 Instrument Air Supply Check to Accum. 2165-S-1017 H-13 6135 2 C 0/C C Tk. I B-SB (Series with I IA-789)

I IA-789 Instrument Air Supply Check to Accum. 2165-S-1017 H-13 6135 2 C 0/C C Tk. IB-SB (Series with IIA-788)

Code Test Requirements Verify reverse flow closure capability nominally every 3 months per the requirements of OM-10, Para. 4.3.2.

Basis for Relief It is impractical to perform a full-stroke closure exercise of the subject check valve during power operation or during cold shutdowns. The 0.75 inch boundary check valves isolate the non-safety related instrument air supply lines to the safety related air accumulators for the containment vacuum relief system outside containment isolation valves ICB-2 and ICB-6.

The primary function of the vacuum relief system is to assure the structural integrity of the containment building as a result of an inadvertent actuation of the containment spray system which causes a partial vacuum inside containment. Makeup air from outside of the containment will flow in to containment when ICB-2 and/or I CB-6 open when containment pressure (vacuum) reaches a predetermined setpoint (-1.0 in w.g.).

The instrument air system provides air to butterfly valves I CB-2 (TK 1A-SA) and 1CB-6 (ITK 1B-SB) actuator accumulators. The butterfly valves (ICB-2 and ICB-6) fail-closed upon loss of instrument air and use the air accumulators for three strokes. Each of the instrument air supply lines to the accumulators contains two simple check valves in series with no intermediate test connections for individual valve closure verification. These valves provide isolation in the event of a failure of the non-safety related instrument air supply. Only one check valve is required in order to meet the safety class interface criteria of ANSI N18.2a-1975 "Revision and Addendum to Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactors" as referenced in the HNP FSAR. It is not practical to verify the full-stroke closure of these valves utilizing non-intrusive diagnostic methods due to their size. As identified in section 4.1.1 of USNRC NUREG-1482 "Guidelines for Inservice Testing at Nuclear Power Plants", "Ifonly one of the two valves is credited in the safety analysis, then verification that the pair of valves is capable of closing is acceptable for IST. Ifrelief is requested on this basis, both valves must be included in the IST program and be subject to equivalent quality assurance criteria."

Alternate Test These valves shall be tested as a pairs as identified in section 4.1.1 of USNRC NUREG-1482 each refueling outage since only one of the two valves is required by the system design. Pair I/I will consist of valves 1IA-786 & I IA-787. Pair II2 will consist of valves I IA-788 and I IA-789. These valves and the air accumulators are presently tested as a pair by a pressure decay test of the subject valves and associated accumulator.

Since all of the subject valves are ASME Section III Class 2 valves, they will have equivalent quality assurance requirements.

Approval Status NRC review and approval is pending. This relief request expires on 2/2/99 unless approved by the NRC.

Revision 0 Page 91 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.4 Valve Relief Requests MS-VRI Component Flow Diagram Dwg System Safety OM Normal Safety Description ID Coo rd Class Cat. Position Position I MS-71 MS "B" to AFW Turbine Check Vlv 2165-S-542 H-7 3020 3 C C 0/C I MS-73 MS "C" to AFW Turbine Check Vlv 2165-S-542 K-7 3020 3 C C 0/C Code Test Requirements Verify reverse flow closure capability nominally every 3 months per the requirements of OM-IO, Para. 4.3.2.1.

Basis for Relief It is impractical to verify a full-stroke close exercise of these valves during power operations or during cold shutdowns due to the lack of the necessary test connections to verify valve closure.

During plant operation, one of the purposes of the main steam system is to deliver steam from the secondary side of the steam generators to the main turbine throttle valves at the required steam conditions. Two 6-inch supply lines located upstream of the main steam isolation valves are provided on steam lines B and C for the operation of the auxiliary feedwater pump turbine.

The auxiliary feedwater system serves as a backup system for supplying feedwater to the steam generators when the main feedwater system is not available. In order to provide steam to the auxiliary feedwater pump turbine, the lines from both the B and C steam generators have a motor-operated valve, check valve, and then come together into a common header.

These check valves perform a safety function in the closed position to provide a redundant isolation to upstream motor operated valve (I MS-70 and I MS-72) in the event of an upstream main steam line break. This function would ensure adequate steam supply to the auxiliary feedwater pump turbine in the event of a failure of the upstream motor operated valve to close.

During plant operation, the steam supply the auxiliary feedwater pump turbine is normally isolated. The auxiliary feedwater turbine driven pump is tested on a 31 day frequency in accordance with the HNP Technical Specifications which provides a only a partial stroke exercise of the subject valves to the open position due to the auxiliary feedwater pump being circulated to the condensate storage tank during normal plant operation. In order to verify a part-stroke exercise of the subject valves to the open position (as required by the code), steam can only be supplied to the auxiliary feed pump turbine from one supply source which requires that the upstream motor-operated valve for the idle steam supply line be isolated. During this test, closure verification of the check valve is not possible since there are no test connections between the subject check valves and the upstream motor-operated valves to monitor the pressure upstream of the subject check valves. The use of non-intrusive techniques to verify closure of the subject valves by isolating steam flow (cessation of flow) is not considered practical due to the high temperature of the steam and the need to remove insulation.

Alternate Test Full-stroke closure of the subject valves will be verified by a sample disassembly and inspection program as outlined in NRC Staff Position 2 in USNRC Generic Letter 89-04 "Guidance On Developing Acceptable Inservice Testing Programs."

The subject valves are of the same design (manufacturer, size, model number and materials of construction) and have the same service conditions including valve orientation and together consist of one group. One of the subject valves shall be disassembled each refueling outage. During valve disassembly, the valve internals will be visually inspected for worn or corroded parts, and the valve disk shall be manually exercised. Ifthe disassembled valve is not capable of being full-stroke exercised or ifthere is binding or failure of the valve internals, the other valve in this group shall also be disassembled, inspected, and manually full-stroke exercised during the same refueling outage.

Approval Status The use of NRC Staff Position 2 in USNRC Generic Letter 89-04 is approved by the USNRC.

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.4 Valve Relief Requests SI-VR1 Component Dwg SSystem Safety OM Normal Safety Description Flow Diagram t ID Coord Class Cat. Position Position ISI-249 Sl Accumulator "A" Discharge Check 2165-S-1309 D-6 2090 I A/C C 0/C Vlv (PIV)

I S1-250 Sl Accumulator "A" Discharge Check 2165-S-1309 D-3 2090 I A/C C 0/C Vlv (PIV)

I SI-251 SI Accumulator "B" Discharge Check 2165-S-1309 G-6 2090 I A/C C 0/C Vlv (PIV)

I SI-252 Sl Accumulator "B" Discharge Check 2165-S-1309 G-3 2090 I A/C C 0/C Vlv (PIV)

I SI-253 Sl Accumulator "C" Discharge Check 2165-S-1309 J-6 2090 I A/C C 0/C Vlv (PIV)

I SI-254 Sl Accumulator "C" Discharge Check 2165-S-1309 J-3 2090 I A/C C 0/C Vlv (PIV)

Code Test Requirements Verify forward flow operability nominally every 3 months per the requirements of OM-IO, Para.4.3.2.

Basis for Relief It is impractical to full or part-stroke exercise these valves during power operation or during cold shutdowns. The normal operating pressure of the safety injection accumulator is insufficient to inject water into the RCS (approximately 2235 psig) during normal plant operation. The subject check valves are 12 inch, stainless steel swing check valves located in the safety injection accumulator cold leg injection lines.

The passive safety injection system cold leg accumulators are pressure vessels normally filled with a 2400 to 2600 ppm boron solution and pressurized with nitrogen. The safety injection accumulator tanks normally contain approximately 925 cubic feet of water and 525 cubic feet of nitrogen pressurized to between 585 to 665 psig. One accumulator is connected to the cold leg of each reactor coolant loop and is normally isolated by two check valves in series. Additionally, a normally open and de-energized motor-operated valve is located upstream of the subject check valves. In the event of a large break, the reactor coolant system is rapidly depressurized and a high flow rate is required to limit possible core damage. The accumulators will automatically discharge when the RCS pressure falls below that of the accumulator. One safety function for the subject valves is to open to allow safety injection accumulator inventory to flow to the reactor coolant system as described above.

Alternate Test A full-stroke opening exercise of the subject valves will be verified by a sample disassembly and inspection program as outlined in NRC Staff Position 2 in USNRC Generic Letter 89-04 "Guidance On Developing Acceptable Inservice Testing Programs." The subject valves are of the same design (manufacturer, size, model number and materials of construction) and have the same service conditions including valve orientation and together consist of two groups.

Group //I consists of the check valves closest to the safety injection accumulators (I SI-249, I SI-251 and I S1-253). Group

//2 consists of the check valves closest to the reactor coolant system (ISI-250, I SI-252, and I SI-254). One of the subject valves in each group shall be disassembled each refueling outage. During valve disassembly, the valve internals will be visually inspected for worn or corroded parts, and the valve disk shall be manually exercised. Ifthe disassembled valve is not capable of being full-stroke exercised or ifthere is binding or failure of the valve internals, the other two valves in the specific group shall also be disassembled, inspected, and manually full-stroke exercised during the same refueling outage.

Valves will be part stroke open exercised after reassembly.

Approval Status The use of NRC Staff Position 2 in USNRC Generic Letter 89-04 is approved by the USNRC.

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdown Justifications AF-CS J1 Component Flow Diagram Dwg System Safety OM Normal Safety Description ID Coord Class Cat. Position Position I AF-102 FW "B" Preheater Bypass Iso Vlv (CIV) 2165-S-544 F-5 3065 2 B 0 C I AF-64 F W "A" Preheater Bypass Iso Vlv(CIV) 2165-S-544 C-6 3065 2 B 0 C I AF-81 FW "C" PreheaterBypasslsoVlv(CIV) 2165-S-544 E-7 3065 2 B 0 C Code Test Requirements Active Category B valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.2.1.

Deferred Test Justification These six inch valves are normally open to supply approximately 18 to 20% of the normal feedwater flow to the steam generators via the auxiliary feedwater nozzles. This function is intended to reduce steam generator tube vibration by redistribution of feedwater flow. Exercising these valves closed quarterly during normal operation would interrupt normal feedwater flow rates possibly causing steam generator transients which would have a significant undesirable effect on plant operations. The valve's control circuitry is not provided with partial stroke capability.

Alternate Test (STC) Stroke time closed at (CS) cold shutdown (FSC) Fail-safe closed at (CS) cold shutdown (ref. OM- 10, para. 4.2.1.2(c))

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdown Justifications AF-CSJ2 Component Description Flow Diagram Dwg System Safety OM Normal Safety ID Coord Class Cat. Position Position IAF-16 AFWP "IA"Discharge Line Check Vlv 2165-S-544 L-6 3065 3 C C 0/C IAF-31 AFWP "IB" Discharge Line Check Vlv 2165-S-544 L-8 3065 3 C C 0/C Code Test Rcquircments Check valves shall be exercised nominally every 3 months per the requirements of OM-IO, Para. 4.3.2.

Deferred Test JustiTication Normally closed, full stroke open and closed exercising requires operating the motor driven auxiliary feedwater pumps and injecting relatively cold condensate water directly into the hot steam'generators. The introduction of cold water into the hot steam generators during normal operation results in thermal shock to the fee'dwater piping and associated nozzles. Allowing excessive thermal transients on the feedwater piping and nozzles could lead to their premature failure due to thermally induced stress cracking. In addition, to test auxiliary feedwater during normal operation would require starting the auxiliary feedwater pumps and securing the normal feedwater system flow which would have an adverse effect on steam generator water level control potentially causing a forced plant shutdown. Part stroke exercising in the forward direction during normal operation would result in the same consequences as full flow exercising. Quarterly pump testing is done through the pump recirculation lines and the downstream flow control valves automatically close so that the pumps are essentially isolated from each other and reverse flow closure of these pump discharge check valves cannot be verified until full auxiliary feedwater flow is injected into the Steam Generators.

I Alternate Test (SO) Stroke open at (CS) cold shutdown (SC) Stroke close at (CS) cold shutdown (ref. OM- 10, para. 4.3.2.2(c))

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdown Justifications AF-CS J3 Component Dwg System Safety OM Normal Safety Description Flow Diagram S t ID Coord Class Cat. Position Position 1AF-19 AFWP "1A" Pressure Control Vlv 2165-S-544 K-6 3065 3 B T 0 1AF-34 AFWP "1B" Pressure Control Vlv 2165-S-544 K-8 3065 3 B T 0 Code Test Requirements Active Category B valves shall be exercised nominally every 3 months per the requirements of OM-10, Para.4.2.1.

Deferred Test JustiTication Normally throttled, the position of valves 1AF-19 and 1AF-34 is automatically modulated during pump operation to protect against run out conditions. Testing of these valves would require the use of control logic defeating methods, such as temporary jumpers. Defeating the control logic associated with these valves to facilitate testing would render them incapable of performing their modulating function should an auxiliary feedwater initiation signal occur during testing.

Alternate Test (STO) Stroke time open at (CS) cold shutdown (FSO) Fail-safe open at (CS) cold shutdown (ref. OM- 10, para. 4.2.1.2(c))

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdown Justifications AF-CSJ4 Component Dwg System Safety OM Normal Safety Description Flow Diagram S t ID Coord Class Cat. Position Position I AF-201 MD AFWP Discharge Line Check Vlv 2165-S-544 H 5 3065 3 C C 0/C to SG "A" 1AF-202 MD AFWP Discharge Line Check Vlv 2165-S-544 I-S 3065 3 C 0/C to SG "B" I AF-203 MD AFWP Discharge Line Check Vlv 2165-S-544 1-6 3065 3 C 0/C to SG "C" I AF-54 MD AFWP Discharge Line Check Vlv 2165-S-544 G-6 3065 3 C 0 to SG "A" I AF-73 MD AFWP Discharge Line Check Vlv 2165-S-544 H-7 3065 3 C C 0 to SG "C" I AF-92 MD AFWP Discharge Line Check Vlv 2165-S-544 I-S 3065 3 C C 0 to SG "B" Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM-IO, Para. 4.3.2.

Deferred Test Justification Normally closed, full stroke open exercising requires operating the motor driven auxiliary feedwater pumps and injecting relatively cold condensate water directly into the hot steam generators. The introduction of cold water into the hot steam generators during normal operation results in thermal shock to the feedwater piping and associated nozzles. Allowing excessive thermal transients on the feedwater piping and nozzles could lead to their premature failure due to thermally induced stress cracking. In addition, to test auxiliary feedwater during normal operation would require starting the auxiliary feedwater pumps and securing the normal feedwatcr system flow which would have an adverse effect on steam generator water level control potentially causing a forced plant shutdown. Part stroke exercising in the forward direction during normal operation would result in the same consequences as full flow exercising. (Valves IAF-201, I AF-202, and 1AF-203 are verified closed quarterly)

Alternate Test (SO) Stroke open at (CS) cold shutdown (ref. OM-10, para. 4.3.2.2(c))

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval t 5.5 Component ID 1AF-117 lAF-136 Valve Cold Shutdown Justifications Description Turbine Driven AFWP Discharge Line Check Vlv TD AFWP Discharge Line Check Vlv to Flow Diagram 2165-S-544 2165-S-544 Dwg System Safety OM Normal Safety Coord L-10 3065 G-6 3065 3

3 C C

C AF-CSJ5 Class Cat. Position Position C 0 0

IIAII IAF-142 TD AFWP Discharge Line Check Vlv to 2165-S-544 H-9 3065 3 C C SG IIBll 1AF-148 TD AFWP Discharge Line Check Vlv to 2165-S-544 G-8 3065 3 C C 0 SG IICII 1AF-204 TD AFWP Discharge Line Check Vlv to 2165-S-544 H-7 3065 3 C C 0/C SG "A" 1AF-205 TD AFWP Discharge Line Check Vlv to 2165-S-544 H-10 3065 3 C C 0/C SG II/II 1AF-206 TD AFWP Discharge Line Check Vlv to 2165-S-544 H- 1 1 3065 3 C C 0/C SG IIClt Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.3.2.

Deferred Test Justification Normally closed, full stroke exercising open requires operating the turbine driven auxiliary feedwater pump and injecting relatively cold condensate water directly into the hot steam generators. The introduction of cold water into the hot steam generators during normal operation results in thermal shock to the feedwater piping and associated nozzles. Allowing excessive thermal transients on the feedwater piping and nozzles could lead to their premature failure due to thermally induced stress cracking. ln addition, to test auxiliary feedwater during normal operation would require starting the auxiliary feedwater pumps and securing the normal feedwater system flow which would have an adverse effect on steam generator water level control potentially causing a forced plant shutdown.

Part stroke exercising in the forward direction during normal operation would result in the same consequences as full flow exercising. The only source of steam to the steam driven turbine is from the main steam system. To operate the turbine requires that the steam generators be producing sufficient steam to drive the turbine. The control of steam generator water level when producing steam is much more critical than during the refilling process when the motor driven pumps are tested.

To perform flow testing during steam production would have a significant impact on steam generator water level control on all three steam generators possibly resulting in a reactor trip. Additionally, full flow testing should be performed at a point when sufflcient steam pressure has been established to minimize a delay in plant restart. (Valves AF-204, 205, and 206 are 1

verified closed quarterly).

Alternate Test (SO) Stroke open at (CS) cold shutdown (ref. OM-10, para. 4.3.2.2(c)

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdown Justifications CE-CSJ1 Component Flow Diagram Dwg System Safety OM Normal Safety Description Coord Class Cat. Position Position ICE-36 CST to MDAFWP "A" Inlet Check Vlv 2165-S-545 H-7 3070 3 C C 0/C ICE-46 CST to MDAFWP "B" Inlet Check Vlv 2165-S-545 H-8 3070 3 C C 0/C ICE-56 CST to TDAFWP Inlet Check Vlv 2165-S-545 H-9 3070 3 C C 0/C Code Test Requirements, Check valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.3.2.

Deferred Test JustiTication Normally closed, full stroke open testing requires operating the auxiliary feedwater pumps and injecting relatively cold condensate water directly into the hot steam generators. The introduction of cold water into the hot steam generators during normal operation could result in thermal shock to the feedwater piping and associated nozzles. Allowing excessive thermal transients on the feedwater piping and nozzles could lead to their premature failure due to thermally induced stress cracking. In addition, to test auxiliary feedwater during normal operation would require starting the auxiliary feedwater pumps and securing the normal feedwater system flow which would have an adverse effect on steam generator water level control potentially causing a forced plant shutdown. Quarterly pump testing is done through the pump recirculation lines at less than full flow conditions.

Alternate Test (PSO) Partial stroke open (Q) quarterly (SO) Stroke open at (CS) cold shutdown (ref. OM-10, para. 4.3.2.2(b)

(Valves are verified closed at Refueling Outage per Relief Request CE-VRI)

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0 0

8NP-IST-002 HNP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdown Justifications CP-CS J1 Component Dwg S t Safety OM Normal Safety Description Flow Diagram System ID Coord Class Cat. Position Position ICP-I Containment Pre-Entry Purge Exhaust 2165-S-1017 E-15 8170 2 A LC C Vlv (CIV)

I CP-10 Containment Pre-Entry Purge Makeup 2165-S-1017 G-16 8170 2 A LC C Vlv (CIV)

I CP-4 Containment Pre-Entry Purge Exhaust 2165-S-1017 E-16 8170 2 A LC C Vlv (CIV)

I CP-7 Containment Pre-Entry Purge Makeup 2165-S-1017 G-15 8170 2 A LC C Vlv (CIV)

Code Test Requirements Active Category A valves shall be exercised nominally every 3 months per the requirements of OM-IO, Para.4.2.1.

Deferred Test Justification Normally closed, these 42 inch valves are maintained in the locked closed position during power operation and are tagged out of service. The only time the active function of the valves must be operable is during modes 5 or 6 when containment closure (core alterations) is required and the valves are in operation for containment purge. In accordance with OM- I 0, paragraph 4.2.1.7, these valves will be exercised within 3 months prior to the time they are required to be operable during refueling outages. Each valve's passive function of maintaining containment integrity applies to modes 1-4 and will be tested in accordance with IOCFR50, Appendix J.

Alternate Test (STC) Stroke time closed at (CS) cold shutdown or prior to being made operable for containment closure per OM- IO, para.

4.2.1.7.

(FSC) Fail-safe closed at (CS) cold shutdown or prior to being made operable for containment closure per OM- I 0, para.

4.2.1.7.

(ref. OM-IO, para. 4.2.1.2(c))

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdown Justifications CS-CSJ1 Component Dwg Safety OM Normal Safety Description Flow Diagram System Coord Class Cat. Position Position ICS-I RCS Letdown Line Iso Vlv 2165-S-1303 A-3 2060 I B 0 C I CS-I I Letdown Iso (CIV) 2165-S-1303 A-17 2060 2 A 0 C ICS-2 RCS Letdown Line Iso Vlv 2165-S-1303 A-3 2060 I B 0 C ICS-238 Charging Line Iso Vlv - CIV (otbd) 2165-S-1303 B-17 2060 2 A 0 0/C Code Test Requirements Active Category A and B valves shall be exercised nominally every 3 months per the requirements of OM- IO, Para. 4.2.1.

Deferred Test Justification Normally open, these valves are located in the normal letdown and charging lines to the RCS. Exercising these valves closed quarterly during normal operation would interrupt normal RCS charging or letdown flow which could cause pressurizer level control transients potentially resulting in a reactor trip. Failure of a letdown valve in the closed position coincident with normal charging flow could result in a high RCS water level trip. Additionally, closure of ICS-238 would isolate charging flow to the regenerative heat exclianger resulting in high letdown temperatures. Reestablishing flow to the heat exchanger could lead to thermal shocking resulting in premature failure. The control circuitry associated with these valves is not provided with partial stroke capability.

Alternate Test (STC) Stroke time closed at (CS) cold shutdown (FSC) Fail-safe closed at (CS) cold shutdown (ref. OM-10, para. 4.2.1.2(c))

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdo>vn Justifications CS-CSJ2 Component Flow Diagram Dwg System Safety OM Normal Safety Description ID Coord Class Cat. Position Position I CS-231 Charging Flow Control Vlv 2165-S-1305 H-4 2060 2 B T 0 I CS-235 Charging Line Iso Vlv 2165-S-1305 H-2 2060 2 B 0 0/C Code Test Requirements Active Category B valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.2.1.

Deferred Test JustiTication I CS-231 is normally throttled and ICS-235 is normally open. These valves are located in the normal charging line to the RCS. Exercising these valves quarterly during normal operation would interrupt normal RCS charging flow which could cause pressurizer level control transients potentially resulting in a reactor trip. The interruption of normal charging flow would also result in high letdown temperatures. The control circuitry associated with these valves is not provided with partial stroke capability.

Alternate Test I CS-231 (STO) Stroke time open at (CS) cold shutdown (FSO) Fail-safe open at (CS) cold shutdown (ref. OM-IO, para. 4.2.1.2(c))

t I CS-235 (STC) Stroke time closed at (CS) cold shutdown (ref. OM-10, para. 4.2.1.2(c))

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdown Justifications CS-CS J3 Component Dwg System Safety OM Normal Safety Description Flow Diagram $ t ID Coord Class Cat. Position Position I CS-165 VCT Outlet Iso - LCV-I ISC 2165-S-1305 G-I I 2060 2 B 0 C I CS-166 VCT Outlet Iso - LCV-I I SE 2165-S-1305 G-I I 2060 2 B 0 C I CS-291 CSIP Suction from RWST Iso Vlv 2165-S-1305 1-12 2060 2 B C 0/C LCV-115B I CS-292 CSIP Suction from RWST Iso Vlv 2165-S-1305 K-12 2060 2 B C 0/C LCV- I I 5D Code Test Requirements Active Category B valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.2.1.

Deferred Test JustiTication I CS-165 and I CS-166 are normally open and I CS-291 and I CS-292 are normally closed. These isolation valves are located in the charging pump suction supply lines from the volume control tank (VCT) and the refueling water storage tank (RWST). These valves are designed with interlocks which prevents both sets of valves from simultaneously being in the same position. Therefore, exercising these valves quarterly would result in aligning the RWST to the suction of the charging pumps. This alignment would allow RWST inventory, with its high boric acid concentration, to be injected into the RCS via the charging line and the RCP pump seals causing power fluctuations and possible plant shutdown. The control circuitry associated with these valves is not provided with partial stroke capability.

Alternate Test 1 I CS-165 and I CS-166 (STC) Stroke time closed at (CS) cold shutdown (ref. OM-10, para. 4.2.1.2(c))

I CS-291 and I CS-292 (STO) Stroke time open at (CS) cold shutdown (STC) Stroke time closed at (CS) cold shutdown (ref. OM-10, para. 4.2.1.2(c))

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0 HNP-IST-002 HiilP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdown Justifications CS-CSJ4 ComPonent Flow Diagram Dwg System Safety OM Normal Safety Description ID Coord Class Cat. Position Position I CS-279 BAT Pumps to CSIP Supply Check Vlv 2165-S-1305 J-17 2060 2 C C 0 Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM- IO, Para. 4.3.2.

Deferred Test Justification Normally closed, this check valve is located in the supply line to the charging pump suction header from the boric acid filter. Forward flow exercising this check valve quarterly during power operation would require injecting a highly concentrated boric acid solution from the boric acid storage tanks into the RCS via the operating charging pump. Injecting a highly concentrated boric acid solution into the RCS would result in severe power fluctuations and the possible shutdown of the reactor. Partial stroke exercising this check valve would result in the same consequences as full stroke exercising.

Alternate Test (SO) Stroke open at (CS) cold shutdown (ref. OM- 10, para. 4.3.2.2(c))

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdown Justifications CS-CSJ5 Component Dwg Safety OM Normal Safety Description Flow Diagram System ID Coord Class Cat. Position Position ICS-294 RWST to CSIP Suction Supply Check 2 l65-S-l305 K-14 2060 2 C C 0/C Vlv Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.3.2.

Dcfcrrcd Test Justification Normally closed, this simple check valve is located in the supply line from the RWST to the charging pump's suction header. The valve is not provided with position indication and has no design provisions (such as test connections) to facilitate reverse exercising. To verify reverse flow closure capability quarterly during power operation would require opening the downstream power operated valves to allow the check valve to communicate with the static pressure of the VCT. Furthermore, aligning the RWST to the charging pump's suction header would allow injection of the highly borated solution contained in the RWST into the RCS via the charging pumps. This RCS injection from the RWST would result in severe power fluctuations and possible plant shutdown.

Altcrnatc Test (SC) Stroke closed at (CS) cold shutdown (ref. OM- l 0, para. 4.3.2.2(c))

(ref. CS-ROJ3 for partial and full stroke open)

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdown Justifications CS-CS J6 Component Flow D. Dwg Safety OM Normal Safety Description Fl Diagram t System S

Coord Class Cat. Position Position ICS-775 CSIP Supply Check Vlv From The RHR 2165-S-1305 J-13 2060 2 C C 0/C IB Heat Exchanger I CS-776 CSIP Supply Check Vlv From The RHR 2165-S-1305 K-13 2060 2 C C 0/C IA Heat Exchanger Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM- IO, Para. 4.3.2.

Deferred Test JustiTication Normally closed, these simple check valves are located in the supply lines from the RHR heat exchangers to the charging pump's suction header and are utilized during the recirculation phase of emergency core cooling. Forward exercising these check valves would require starting the associated RHR pump, opening upstream power operated valves I RH-25 and I RH-63, and establishing flow through the RHR heat exchangers from the RWST to the charging pump suction header. This is not possible during power operation. This flow path would not only upset the normal charging and letdown flow rates but would also result in severe power fluctuations and plant shutdown due to the injection of the highly borated contents of the RWST into the RCS via the charging pumps. Partial exercising these check valves to the open position would result in the same consequences as full exercising. The system piping containing these valves has no design provisions (such as test connections) to facilitate reverse exercising. The valves do communicate with static pressure from the VCT. However, test connections are not provided for differential pressure measurement between the check valves and the upstream normally closed power operated valves. Reverse flow closure capability is best able to be verified when the charging pumps can be removed from service and an abnormal RHR system alignment can be established.

Alternate Test (SO) Stroke open at (CS) cold shutdown (SC) Stroke closed at (CS) cold shutdown (ref. OM-10, para. 4.3.2.2(c))

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HNP-IST-002 HNP IST Program Plan - 2nd Intcval 5.5 Valve Cold Shutdown Justifications CS-CSJ7 Component Description Flow Diagram Dwg Safety OM Normal Safety System Coord Class Cat. Position Position I CSC80 Alternate Charging Line Iso Vlv 2165-S-1303 B-4 2060 2 B C 0/C I CS-483 RCS Alternate Charging Line Check Vlv 2165-S-1303 B-3 2060 I C C 0/C I CS-486 RCS Alternate Charging Line Check Vlv 2165-S-1303 B-3 2060 I C C 0/C I CS-492 Normal Charging Line Iso Vlv 2165-S-1303 C-4 2060 2 B 0 0/C Code Test Requirements Active Category B valves shall be exerc'ised nominally every 3 months per the requirements of OM-IO, Para.4.2.1.

Check valves shall be exercised nominally every 3 months per the requirements of OM- IO, Para. 4.3.2.

Deferred Test Justification Normally closed, exercising valves I CS-480, ICS-483, ICS-486 quarterly during power operation has been determined to .

cause thermal cycling of the alternate charging path piping which could lead to premature failure. This problem has been documented by Westinghouse in letter CQL-90-562, dated 09/27/90. Likewise, the normally open normal charging line isolation valve ICS-492 cannot be exercised since this would require flowing through the alternate path to avoid isolation of normal charging and letdown flow. These valves will be tested on a cold shutdown frequency. Partial stroke exercising of the alternate charging line check valves would result in the same consequences previously discussed, The control circuitry associated with the Category B valves is not provided with partial stroke capability.

Altcrnatc Test I CS-480 (STO) Stroke time open at (CS) cold shutdown (FSO) Fail-safe open at (CS) cold shutdown (ref. OM-IO, para. 4.2.1.2(c))

I CS-492 (STC) Stroke time closed at (CS) cold shutdown (FSO) Fail-safe open at (CS) cold shuidown (ref. OM- IO, para. 4.2.1.2(c))

ICS-483 and ICS-486 (SO) Stroke open at (CS) cold shutdown (ref. OM-10, para. 4.3.2.2(c))

(valve is (SC) at (RO) per CS-ROJ I)

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdown Justifications CS-CSJS Component t Flow Diagram Dwg System Sa fety OM Normal Safety Description De c Coord Class Cat. Position Position I CS-167 VCT Outlet Check Vlv 2165-S-1305 -

G-11 2060 2 A/C 0 C Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.3.2.

Deferred Test Justiflcation Normally open, this simple check valve is located in the discharge piping from the volume control tank (VCT) to the charging pump's suction header. Reverse exercising this check valve quarterly during power operation would require isolation of the VCT outlet piping, interruption of normal charging flow, and the realignment of the charging pumps suction to the RWST as the alternate supply source. Interrupting normal RCS charging flow could cause pressurizer level control transients potentially resulting in a reactor trip. Realignment to the RWST as the charging pump's alternate supply source would allow RWST inventory, with its high boric acid concentration, to be injected into the RCS via the normal charging line and the RCP pump seals causing severe power fluctuations and possible plant shutdown.

Alternate Test (SC) Stroke closed at (CS) cold shutdown (ref. OM-10, para. 4.3.2.2(c))

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval t 5.5 ID I FW-l59 1FW-217 Valve Cold Shutdown Justifications Component (CIV)

Description Feedwater Line Iso Vlv to S/G "A" Flow Diagram 2165-S-544 Feedwater Line Iso Vlv to S/G "C" (CIV) 2165-S-544 Dwg System Safety OM Normal Safety Coord B-6 D-4 3050 3050 2

2 B

B 0 FW-CS J1 Class Cat. Position Position 0 C C

I FW-277 Feedwater Line Iso Vlv to S/G "B" (CIV) 2165-S-544 E-4 3050 2 B 0 C Code Test Rcquiremcnts Active Category B valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.2.1.

1 Deferred Test Justification Normally open, full stroke closed exercising the feedwater isolation valves quarterly during normal operation would result in a loss of normal feedwater flow to the associated Steam Generator except for that provided by the auxiliary feedwater line. Isolation of normal feedwater flow during power operation could potentially cause a severe steam generator level transient which could result in a plant trip, and would initiate an auxiliary feedwater system actuation signal unnecessarily.

The feedwater isolation valves are provided with partial stroke capability.

Alternate Test (PSC) Partial stroke closed (Q) quarterly.

(STC) Stroke time closed at (CS) cold shutdown (FSC) Fail-safe closed at (CS) cold shutdown (ref. OM- I 0, para. 4.2.1.2(b)

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdown Justifications FW-CS J2 Component Dwg System Safety OM Normal Safety Description Flow Diagram S Coord Class Cat. Position Position I FW-158 Feedwater Injection Check Vlv to S/G 2165-S-544 B7 3050 2 C 0 C II AII I FW-216 Feedwater Injection Check Vlv to S/G 2165-S-544 D-5 3050 2 C 0 C NCII I FW-276 Feedwater Injection Check Vlv to S/G 2165-S-544 E-4 3050 2 C 0 1lBlt Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM- IO, Para. 4.3.2.

Deferred Test Justification Normally open, full stroke closed exercising the feedwater injection check valves is not possible quarterly during power operation due to the necessity of isolating normal feedwater flow to the associated Steam Generator. Isolation of feedwater flow during normal operation would cause a loss of steam generator level control resulting in a plant trip. The normal method to verify reverse flow closure is to perform a leak test or establish a differential pressure across the valve seat. This can only be performed during cold shutdowns when a differential pressure may be established across the valve seat by allowing steam generator head pressure to communicate with the downstream side of the valve seat while simultaneously measuring line pressure upstream of the seat.

t Alternate Test (SC) Stroke close at (CS) cold shutdown (ref. OM-10, para. 4.3.2.2(c))

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdo>vn Justifications IA-CSJl Flow Diagram Dwg System Safety OM Normal Safety Description Coord Class Cat. Position Position I IA-819 Instrument Air Supply to Containment 2165-S-801 C-3 6135 2 A 0 C Iso Vlv (CIV)

Code Test Requirements Active Category A valves shall be exercised nominally every 3 months per the requirements of OM- IO, Para. 4.2.1.

Def'erred Test Justification Normally open, instrument air supplies a number of components inside containment which are dependent upon instrument air to remain operable for support of normal plant operation. Exercising this valve to the closed position quarterly during normal operation would deprive these components of their normal actuating air supply. Since the largest majority of these components have no backup air supply, component realignment or a loss of sensing capability is likely to occur upon interruption of their air supply. Loss of operability or mispositioning of these components could result in operating transients and a possible forced plant shutdown. The control circuitry for this valve is not provided with partial stroke capability.

Alternate Test (STC) Stroke time closed at (CS) cold shutdown (FSC) Fail-safe closed at (CS) cold shutdown (ref. OM-10, para. 4.2.1.2(b))

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdown Justifications MS-CSJ1 Component Dwg Safety, OM Normal Safety Description Flow Diagram $ t System Coord Class Cat. Position Position I MS-80 Main Steam Iso Vlv (MSIV) for MS Hdr 2165-S-542 D-9 3020 2 B 0 C "A" (CIV)

I MS-82 Main Steam Iso Vlv (MSIV) for MS Hdr 2165-S-542 G-9 3020 2 B 0 C "B"(CIV)

I MS-84 Main Steam Iso Vlv (MSIV) for MS Hdr 2165-S-542 J-9 3020 2 B 0 C "C"(CIV)

Code Test Requirements Active Category B valves shall be exercised nominally every 3 months per the requirements of OM-IO, Para.4.2.1.

Deferred Test JustiTication Normally open, full stroke closed exercising of these valves during normal operation isolates one line of steam flow to the turbine. Isolation of a main steam header would cause a severe pressure transient in the associated main steam line possibly resulting in a forced plant shutdown. Additionally, closure of an MSIV, at power, could potentially result in challenging the set point of the main stcam relief valves causing inadvertent liAing. Reducing power level to perform testing without causing a transient would significantly impact plant operations and power production. These valves are provided with partial stroke capability.

l Alternate Test (PSC) Partial stroke closed (Q) quarterly.

(STC) Stroke time closed at (CS) cold shutdown (FSC) Fail-safe closed at (CS) cold shutdown (ref. OM-10, para. 4.2.1.2(b))

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdown Justifications MS-CSJ2 Component ~ Dwg Safety OM Normal Safety Description Flow Diagram System S

Coord Class Cat. Position Position 1 MS-71 MS "B" to AFW Turbine Check Vlv 2165-S-542 H-7 3020 3 C C 0/C I MS-73 MS "C" to AFW Turbine Check Vlv 2165-S-542 K-7 3020 3 C C 0/C Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.3.2.

Deferred Test JustiTication Normally closed, full flow stroke open exercising of these check valves would require running the Auxiliary Feedwater Pump Turbine at full flow conditions. This is not possible quarterly during power operation as the only flow path that could handle the necessary auxiliary feedwater flow (the feedwater flow that would demand the minimum required steam flow) is into the steam generators. This could result in thermal shock to the feedwater piping and nozzles. The quarterly pump test is performed with flow through a minimum flow line and is not a full flow test.

Alternate Test (PSO) Partial stroke open (Q) quarterly (SO) Stroke open at (CS) cold shutdown (ref. OM-10, para. 4.3.2.2(b))

Closed testing performed per MS-VR Revision 0 Page 113 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdown Justifications RC-CS JI Component Dwg Safety OM Normal Safety Description Flow Diagram System Coord Class Cat. Position Position I RC-114 PRZ PORV PCV-444B 2165-S-1301 H-1 2050 I B C 0/C I RC-116 PRZ PORV PCV-445B 2165-S-1301 F- I 2050 I B C C I RC-118 PRZ PORV PCV-445A 2165-S-1301 E- I 2050 1 B C 0/C Code Test Requirements Active Category B valves shall be exercised nominally every 3 months per the requirements of OM- IO, Para. 4.2.1.

Deferred Test Justification Normally closed, the PORVs are controlled by the Pressurizer Overpressure Protection System, which automatically opens two of the three valves at a preset pressure. At power, set pressures are established to limit undesirable opening of the spring-loaded pressurizer safety valves. The PORVs are relied upon during reactor startup and shutdown to protect the RCS from potential low temperature overpressurization transients. In the event of a steam generator tube rupture, the PORVs may be required to open for accident mitigation by providing a means for rapid manual depressurization of the RCS. Due to the high probability for the PORVs to stick in the open position or failure to provide a leak tight barrier when closed, quarterly exercising during power operation is not practical. In accordance with Generic Letter 90-06, and the guidelines provided in NUREG-1482, Section 4.4.1, these valves will be tested on the way to cold shutdown during Modes 3 or 4, prior to LTOPS operation in Mode 5 or 6 at startup, and during Modes 3 or 4 upon return to power.

t Alternate Test (STO) Stroke time open at (CS) cold shutdown (STC) Stroke time closed at (CS) cold shutdown (FSC) Fail-safe closed at (CS) cold shutdown (ref. OM-10, para. 4.2.1.2(c))

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0 HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdown Justifications RC-CS J2 Com onent Compo Dwg Safety OM Normal Safety Description Flow Diagram System ID Coord Class Cat. Position Position I RC-900 Reactor Vessel Head Vent Vlv 2165-S-1301 A-7 2050 2 B C 0/C I RC-901 Reactor Vessel Head Vent Vlv 2165-S-1301 A-7 2050 2 B C 0/C I RC-902 Pressurizer Steam Space Vent Vlv 2165-S-1301 C-7 2050 2 B C 0/C I RC-903 Pressurizer Steam Space Vent Vlv 2165-S-1301 B-7 2050 2 B C 0/C I RC-904 Vent Path to the Containment 2165-S-1301 C-5 2050 2 B C 0/C Atmosphere I RC-905 Vent Path to the PRT 2165-S-1301 A-8 2050 2 B C 0/C Code Test Requirements Active Category B valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.2.1.

Deferred Test Justification These hydraulic assisted pilot operated valves were installed subsequent to the TMI accident, and serve as the RCS high point vent valves. Their intended function is to provide reactor head venting capabilities during a natural circulation cool-down evolution. The valves are routinely used during cold shutdown to provide a path for RCS venting.

Technical Specification 3.4.11 requires that one vent path from the reactor pressure vessel head and one vent path from the pressurizer be operable and closed during operation. Testing of these valves quarterly during power operation, with subsequent failure in the open position, could result in uncontrolled blowdown of RCS inventory to the pressurizer relief tank or containment atmosphere should the downstream block valves inadvertently open or experience excessive leakage.

Experience of this condition precipitated NLS-87-247 on I I/23/19S7 and susequent License Ammendment NPF-63 //4 to remove the quaterly test requirements from T.S.3.4.11. Further evidence of this condition related disparity is addressed by ASME 81-BVP-39 (April of 19SI) "Spurious Opening of Hydraulic Assisted Pilot Operated Valves". The control circuitry associated with these valves is not provided with partial stroke capability.

Alternate Test (STO) Stroke time open at (CS) cold shutdown (STC) Stroke time closed at (CS) cold shutdown (FSC) Fail-safe closed at (CS) cold shutdown (ref. OM-10, para. 4.2.1.2(c))

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lJ HNP-IST-002 HNP IST Program Plan - 2nd Inteval t 5.5 Component ID I RH- I I RH-2 Valve Cold Shutdown Justifications Description RCS Loop I-HL to RHR Pump A-SA Iso Vlv (PIV) (CIV)

RCS Loop I-HL to RHR Pump A-SA Flow Diagram 2165-S-1324 2165-S-1324 Dwg System Coord L-3 L-4 S

2085 2085 I

I A A C C

RH-CS Jl Safety OM Normal Safety Class Cat. Position Position 0/C 0/C Iso Vlv (CIV) (PIV)

I RH-39 RCS Loop 3-HL to RHR Pump B-SB 2165-S-1324 1-3 2085 I A C 0/C Iso Vlv (CIV)(PIV)

I RH-40 RCS Loop 3-HL to RHR Pump B-SB 2165-S-1324 1-4 2085 I A C 0/C Iso Vlv (CIV)(PIV)

Code Test Requirements Active Category A valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.2.1.

Dcfcrrcd Test Justification Normally closed, these RCS pressure isolation valves are located in the RHR pumps suction supply lines from the RCS hot legs. Exercising these valves quarterly during power operation is not possible due to the presence of interlocks which prevent their opening unless RCS pressure has been reduced to below 363 psig. This design feature prevents inadvertent overpressurization of the associated train of RHR. Defeating these interlocks to facilitate testing, with subsequent seat leakage of the inline valve, could lead to an inter-system LOCA by exposing the low pressure RHR system to the high pressure reactor coolant system. Partial valve exercising is precluded for the same reasons as full stroke exercising.

I Altcrnatc Test (STO) Stroke time open at (CS) cold shutdown (STC) Stroke time closed at (CS) cold shutdown (ref. OM-10, para. 4.2.1.2(c))

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdown Justifications SI-CS J1 Component Dwg System Safety OM Normal Safety Description Flow Fl Diagram D S t ID Coord Class Cat. Position Position I SI-134 Sl Low Head to RCS Hot Leg Loops I 2165-S-1308 B-11 2080 I A/C C 0/C (CIV)(PIV)

ISI-135 Sl Low Head to RCS Hot Leg Loop 2 2165-S-1308 C-11 2080 A/C C 0/C (CIV)(PIV)

I SI-136 RCS Hot Leg Loop I Inj Ck Vlv 2165-S-1308 B-17 2080 C C 0/C ISI-137 RCS Hot Leg Loop 2 Inj Ck Vlv 2165-S-1308 C-17 2080 C C 0/C I SI-346 LHSI Train "A" to Cold Legs Inj. Check 2165-S-1310 C-3 2080 2 A/C C 0/C (PIV/CIV)

I SI-347 LHSI Train "B" to Cold Legs Inj. Check 2165-S-1310 E-3 2080 2 A/C C 0/C (PIV/CIV)

ISI-356 LHSI to RCS Cold Leg Loop I (PIV) 2165-S-1310 C-2 2080 I A/C C . 0/C ISI-357 LHSI to RCS Cold Leg Loop 2 (PIV) 2165-S-1310 E-2 2080 I A/C C 0/C ISI-358 LHSI to RCS Cold Leg Loop 3 (PIV) 2165-S-1310 E-2 2080 I A/C C 0/C ISI-Sl RCS Cold Leg Loop I Injection Check 2165-S-1308 B-3 2080 I C C 0/C ISI-82 RCS Cold Leg Loop 2 Injection Check 2165-S-1308 C-3 2080 I C C 0/C 1S1-83 RCS Cold Leg Loop 3 Injection Check 2165-S-1308 D-3 2080 I C C 0/C Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM- IO, Para. 4.3.2.

Defcrrcd Test Justificatio Normally closed, these simple check valves are located in either the low head and/or high head safety injection flow paths to the RCS cold legs or hot legs. Full stroke exercising open of those check valves located solely in the low head safety injection flow path (ISI-346,347,356,356 and 358) can only be performed by injecting RHR flow into the RCS.

Establishing this flow path quarterly during normal operation is not possible. The low pressure RHR pumps are unable to develop sufficient discharge head to overcome the higher RCS operating pressure. Full stroke exercising open of those check valves which are also located in the high head safety injection flow path could be performed utilizing the high pressure charging pumps. However, establishing this flow path would require utilizing the RWST as the supply source and injecting large quantities of highly borated water into the RCS. This would also cause a large thermal transient at the RCS nozzle.

This is not practical quarterly during normal operation due to the potential of causing pressurizer level control problems and severe power fluctuations possibly resulting in a reactor trip. Partial stroke exercising these check valves quarterly during normal operation is prevented for the same reasons as for full exercising.

Alternate Test (SO) Stroke open at (CS) cold shutdown (ref. OM-10, para. 4.3.2.2(c))

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l HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdown Justifications SI-CS J2 Component Dwg Safety OM Normal Safety Description Flow Diagram System ID Coo rd Class Cat. Position Position I SI-359 LHSI Trains "A" and "B" to RCS Hot 2165-S-1310 B-4 2080 2 A C 0/C Legs Loops I and 2 (CIV) (PIV)

Code Test Requirements Active Category A valves shall be exercised nominally every 3 months per the requirements of OM- IO, Para. 4.2.1.

Defcrrcd Test Justification Normally closed, this motor operated valve serves as the second high pressure boundary barrier between the RCS and the low pressure piping of the Residual Heat Removal System. The valve is placed in the open position when switching from the cold leg to hot leg recirculation mode of safety injection. To prevent opening during normal operation the valve is electrically disconnected per Tech. Spec. 4.5.2.8 and administratively maintained closed. Exercising this valve quarterly during normal operation could cause overpressurization of the RHR System piping and result in an inter-system LOCA condition. The control circuitry associated with this valve is not provided with partial stroke capability. Even ifpossible, partial stroke exercising would result in the same consequences as full exercising.

Alternate Test (STO) Stroke time open at (CS) cold shutdown (STC) Stroke time closed at (CS) cold shutdown (ref. OM-10, para. 4.2.1.2(c)

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.5 Valve Cold Shutdown Justifications SI-CS J3 Component Dwg System Safety OM Normal Safety Description Flow Diagram $ t Coord Class Cat. Position Position I SI-182 Accumulator Fill from RWST (CIV) 2165-S-1309 J-16 2090 2 A/C 0/C 0/C Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.3.2.

Deferred Test Justification Normally open/closed, this check valve is located inside primary containment serving as inboard containment isolation valve for the safety injection (Sl) accumulator fill line. It is not provided with position indication. Stroke open verification of this check valve requires feed and bleed of the SI accumulators and monitoring for a level increase or installation of non-intrusive flow instumentation to verify flow.

Testing using the Sl accumulator feed and bleed method is not practical during normal operation because it would require unnecessary cycling of equipment to obtain a detectable level increase (ref. NUREG-1482, Section 2.5.4).

NUREG-1482, Section 3.1.1 states, "...Check valves that can be stroked quarterly, but must be monitored by a non-intrusive technique to verify full stroke, may be fullstoke tested during cold shutdowns or refueling outages ifanother method of verifying full-stroke exists at these plant conditions ...".

Altcrnatc Test (SO) Stroke open at (CS) cold shutdown (ref. OM-10, para. 4.3.2.2(c) and Section 3.1.1 of USNRC NUREG-1482)

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0 HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 Valve Refueling Outage Justifications AF-ROJ1 Component Dwg Safety OM Normal Safety Description Flow Diagram System Coo rd Class Cat. Position Position 1AF-103 FW "B" Preheater Bypass Check Vlv 2165-S-544 G-5 3065 2 C 0 C 1AF-65 FW "A" Preheater Bypass Check Vlv 2165-S-544 C-6 3065 2 C 0 C 1AF-84 FW "C" Preheater Bypass Check Vlv 2165-S-544 E-5 3065 2 C 0 C Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.3.2.

Deferred Test Justification Normally open, the only system design provisions for verification of reverse flow closure of these check valves would require the complete isolation of feedwater to a generator. This method for closure verification involves isolation of the main feedwater, then opening the upstream power operated valve, then verifying a differential pr'essure exists across the valve seat by measuring upstream pressure during the auxiliary feedwater pump full flow test. Test instrumentation must be installed to perform this test method. The only other means to demonstrate proper valve closure capability is by manual exercising during disassembly at refuel outage per OM-10, para. 4.3.2.4(c).

NUREG-1482, Section 4.1.4 states, "... The NRC has determined that the need to setup test equipment is adequate justification to defer backflow testing until a refueling outage...".

Alternate Test (SC) Stroke close at (RO) refueling outage (ref. OM-10, para. 4.3.2.2(e)

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 Valve Refueling Outage Justifications CB-ROJ1 Component Dwg S Safety OM Normal Safety Description Flow Diagram System Coord Class Cat. Position Position PDT-01CB PDT-7680A I Outside Containment 2166-B-431 DP38 n/a 8060 2 C 0 0/C Pressure (CIV)

PDT-01CB PDT-7680A Outside Containment 2166-B-431 DP38 n/a 8060 2 C 0 0/C Pressure (CIV)

PDT-01CB PDT-7680B I Outside Containment 2166-B-431 DP38 n/a 8060 2 C 0 0/C Pressure (CIV)

PDT-01CB PDT-7680B Outside Containment 2166-B-431 DP38 n/a 8060 2 C 0 0/C Pressure (CIV)

PDT-01CP- PDT-OICP-7611S Excess Flow Check 2166-B-431 DP39 n/a 8170 2 C 0 0/C Valve (CIV)

Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM-IO, Para. 4.3.2.

Deferred Test Justification These excess flow check valves are located oustide containment in instrument sensing lines. These valves are normally open by spring force and close with high flow from a downstream instrument line break. The upstream side of these check valves is open to containment atmosphere at negative pressure and does not have test connections. Closure verification of these valves requires installation of test equipment (such as vacuum pump and hoses) to provide flow.

NUREG-1482, Section 4.1.4 states, "... The NRC has determined that the need to setup test equipment is adequate justification to defer backflow testing until a refueling outage...".

Alternate Test (SC) Stroke close at (RO) refueling outage (ref. OM- I 0, para. 4.3.2.2(e)

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 Valve Refueling Outage Justifications CC-ROJ1 Component Dwg System Safety OM Normal Safety Description Flow Diagram S Coord Class Cat. Position Position I CC-211 CCW Supply to RCPs - Inboard CIV 2165-S-1321 F-I 4080 2 A/C 0 0/C I CC-250 CCW Return From RCP Thermal 2165-S-1321 F-16 4080 2 A/C C 0/C Barriers - Inboard CIV ICC-298 CCW Return From RCP Motor Bearing 2165-S-1321 F-13 4080 2 A/C C 0/C Coolers - Inboard CIV Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM-IO, Para. 4.3.2.

Deferred Test JustiTication I CC-211 is normally open and I CC-250 and I CC-298 are normally closed. Testing these valves quarterly during power operation and during cold shutdowns of short duration is not practical due to the interruption of cooling water flow to the RCPs required to align for. the test configuration. These check valves are located inside primary containment serving as inboard containment isolation valves and are not provided with position indication. The only method available to verify reverse flow closure capability of these check valves is by interrupting their normal process functions and performing seat leakage testing. The test connections utilized to perform seat leakage testing are located inside containment. Therefore, it would require containment entry in order to verify their closure capability. Routine containment entry cannot be made quarterly during power operation due to high radiation levels and the potentially harsh environment inside primary containment.

NUREG-1482, Section 4.1.4 states, "... The NRC has determined that the need to setup test equipment is adequate justification to defer backflow testing until a refueling outage...".

g Alternate Test (SC) Stroke close at (RO) refueling outage during Appendix J, Type C, testing (SO) Stroke open at (RO) refueling outage (ref. OM- IO, para. 4.3.2.2(e) and Section 4.1.4 of USNRC NUREG-1482)

I CC-211 only(SO) Stroke open is verified (Q) quarterly Revision 0 Page 122 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 Valve Refueling Outage Justifications CC-ROJ2 Com onent Compon Flow Diagram Dwg System Safety OM Normal Safety Description ID Coord Class Cat. Position Position I CC-556 RHR Htx "A" Press Relief Bypass Line 2165-S-1320 B-7 4080 3 C 0/C 0 Check Vlv I CC-558 RHR Htx "B" Press Relief Bypass Line 2165-S-1320 M-7 4080 3 C 0/C Check Vlv ICC-561 Fuel Pool Heat Exchangers I & 4B 2165-S-1322 SO I J-5 4080 3 C 0 Press. Relief Bypass Line Check ICC-563 Seal Water Hx Shell Side Thermal Relief 2165-S-1322 J-2 4080 3 0 ICC-565 Letdown Hx Shell Side Thermal Relief 2165-S-1322 J-4 4080 3 C 0 0 ICC-567 Vent Condenser Thermal Relief 2165-S-1322 K-7 4080 3 0 0 I CC-569 Recycle Evaporator Condenser Thermal 2165-S-1322 K-11 4080 3 C 0 0 Relief I CC-571 Distillate Cooler Thermal Relief 2165-S-1322 K-9 4080 3 C 0 I CC-573 Fuel Pool Heat Exchangers I & 4A 2165-S-1322 SO I 1-3 4080 3 C 0 Press. Relief Bypass Line Check Code Test Requirements Active Category C valves shall be exercised nominally every 3 months per the requirements of OM-IO, ParaA.3.2.1.

Deferred Test Justification These valves are normally open simple check valves (functioning as thermal relief valves) located on various heat exchangers cooled by component cooling water system. During normal operation, the heat exchanger outlet valves are either throttled or closed to the extent that the thermal relief check valves are normally open. However, no permanent plant instrumentation exists to verify flow through the check valve. The only positive means of verifying the valves are open is to install temporary non-intrusive test equipment.

NUREG-1482, Section 4.1.4 states, "... The NRC has determined that the need to setup test equipment is adequate justification to defer backflow testing until a refueling outage...".

Alternate Test (SO) Stroke open at (RO) refueling outage (ref. OM-IO, para. 4.3.2.2(e)

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 Valve Refueling Outage Justifications CC-ROJ3 Component Description Flow Diagram Dwg System Safety OM Normal Safety ID Coord Class Cat. Position Position'080 I CC-207 CCW Supply To RCPs Iso Vlv 2165-S-1321 E-I 2 B 0 C I CC-208 CCW Supply To RCPs Iso Vlv- 2165-S-1321 F-I 4080 2 A 0 ,

C Outboard CIV I CC-249 CCW Return From RCP Thermal 2165-S-1321 E-15 4080 2 A 0 Barriers - Inboard CIV I CC-251 CCW Return From RCP Thermal 2165-S-1321 E-15 4080 2 A 0 C Barriers - Outboard CIV I CC-252 CCW Return From RCPs Thermal 2165-S-1321 D-15 4080 2 B 0 C Barrier Iso Vlv I CC-297 CCW Return From RCP Mtr. Brg. 2165-S-1321 E 12 4080 2 A 0, Coolers - Inboard CIV ICC-299 CCW Return From RCPs Iso Vlv- 2165-S-1321 E-12 4080 2 A 0 Outboard CIV -.

Code Test Requirements Active Category A and B valves shall be exercised nominally every 3 months per the requirements of OM-IO, Para. 4.2.1.

Deferred Test Justification Normally open, these are the containment isolation and block valves located in the RCP thermal barrier and bearing oil cooler lines. Testing these valves quarterly during power operation and during cold shutdowns of short duration is not practical due to the interruption of cooling water flow to the RCPs. Failure for these valves to open subsequent to closure would result in a complete loss of cooling water flow to the RCPs. A loss of cooling water for more than a few minutes could result in extensive damage to the pumps and pump motors and potentially cause a plant trip. Westinghouse Document I B5710-100-07A states that cooling water must be provided to the pumps at all times when the RCS temperature is above 200'F. Plant procedures indicate that it is desireable to operate the pumps during cold shutdown and that at least one RCP be operating when RSC temperature is > 160 degrees F. Testing during cold shutdown is not practical since cooling water to the reactor coolant pump thermal barriers and motor bearings must be isolated to perfom the test.

This would require all reactor coolant pumps to be stopped.

NUREG-1482, Section 3.1.1.4 indicates the need to stop reactor coolant pumps is adequate justification to defer testing to refuel outages.

Alternate Test (STC) Stroke time closed at (RO) refueling outage when the RCP's can be removed from service.

(ref. OM-IO, para. 4.2.1.2(e))

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 Valve Refueling Outage Justifications CS-ROJ1 Component Flow Diagram Dwg SSystem Safety OM Normal Safety Descri ption t Coord Class Cat. Position Position I CS-344 RCP "A" Seal Water Injection Check 2165-S-1303 K-3 2060 2 A/C 0 0/C Vlv (CIV)

I CS-385 RCP "8" Seal Water Injection Check 2165-S-1303 S01 K-3 2060 2 A/C 0 0/C Vlv (CIV)

I CS-426 RCP "C" Seal Water Injection Check 2165-S-1303 S02 K-3 2060 2 A/C 0 0/C Vlv (CIV)

I CS-471 RCP Seal Water Return & Excess 2165-S-1303 E-16 2060 2 A/C C 0/C Letdown Thermal Relief Check (CIV)

ICS-477 CVCS Normal Charging Line Check 2165-S-1303 B-16 2060 2 A/C 0 0/C Vlv (CIV)

Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements on OM-IO, Para. 4.3.2.

Defcrrcd Test Justificatio I CS-344 and I CS-385 are normally open and I CS-426 and I CS-471 are normally closed. These simple check valves are located inside primary containment serving as inboard containment isolation valves and are not provided with position indication. The only method available to verify reverse flow closure capability of these check valves is by seat leakage testing. The test connections utilized to perform seat leakage testing are located inside containment. Therefore, it would require containment entry and the interruption of the valves'ormal process functions in order to verify their closure capability. Routine containment entry cannot be made quarterly during power operation due to high radiation levels and the potentially harsh environment inside primary containment. Performing this test activity during cold shutdowns is not desirable due to personnel hazards and ALARAconcerns and the requirement to shut down and restart the reactor coolant pumps (RCP)'s. Plant procedures indicate that it is desireable to operate the pumps during cold shutdown and that at least one RCP be operating when RSC temperature is > 160 degrees F.

Alternate Test (SC) Stroke close at (RO) refueling outage during Appendix J, Type C, testing (SO) (ICS-471 only) Stroke open at (RO) refueling outage All other valves (SO) Stroke open is verified (Q) quarterly.

(ref. OM-10, para. 4.3.2.2(e) and Section 4.1.4 of USNRC NUREG-1482 Revision 0 Page 125 of 145

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 Valve Refueling Outage Justifications CS-ROJ2 Component Dwg Safety OM Normal Safety Flow Diagram System Coord Class Cat. Position Position I CS-178 CSIP "IA"Discharge Check Vlv 2165-S-1305 H-7 2060 2 C 0/C 0/C I CS-192 CSIP "IB" Discharge Check Vlv 2165-S-1305 K-7 2060 2 C 0/C 0/C I CS-206 CSIP "IC" Discharge Check Vlv 2165-S-1305 J-7 2060 2 C 0/C 0/C Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.3.2.

Deferred Test Justification Normally open/closed, these charging pump discharge check valves cannot be verified for full flow operability quarterly during normal operation. Normal charging flow is automatically controlled by downstream flow control valve (ICS-231) in response to RCS operating conditions. Injecting full flow into the RCS quarterly during normal operation would require realigning the flow through safety injection lines. This flow would cause an increase in reactor coolant pressure because letdown capacity is less than safety injection capacity. This is considered an ESF actuation which is prohibited by normal operations. Full flow exercising these valves at cold shutdown could result in low-temperature overpressurization of the RCS due to the lack of sufficient expansion volume necessary to establish the design accident flow rate.

Alternate Test (PSO) Partial stroke open (Q) quarterly (SO) Stroke open at (RO) refueling outage (ref. OM-10, para. 4.3.2.2(e))

(SC) Stroke closed is verified (Q)quarterly Revision 0 Page 126 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Intcval 5.6 Valve Refueling Outage Justifications CS-ROJ3 Component Dwg Safety OM Normal Safety Description Flow Diagram System ID Coord Class Cat. Position Position I CS-294 RWST to CSIP Suction Supply Check 2165-S-1305 K-14 2060 2 G C 0/C Vlv Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.3.2.

Deferred Test Justification Normally closed, this check valve is located in the supply line from the RWST to the charging pump's suction header.

Verification of forward flow operability quarterly during power operation would require injecting RWST water into the RCS. Aligning the RWST to the charging pump's suction header would cause injection of the highly borated solution contained in the RWST into the RCS via the charging pumps. This RCS injection from the RWST would result in severe power fluctuations and possible plant shutdown. Partial stroke exercising this check valve quarterly during normal operation is prevented for the same reasons as full flow exercising. Full flow exercising these valves at cold shutdown could result in low-temperature overpressurization of the RCS due to the lack of sufficient expansion volume necessary to establish the design accident flow rate.

Alternate Test (PSO) Partial stroke open at (CS) cold shutdown (SO) Stroke open at (RO) refueling outage (ref. OM-10, para. 4.3.2.2(d))

(SC) Stroke closed is verified per CS-CSl5 Revision 0 Page 127 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 Valve Refueling Outage Justifications CS-ROJ4 Component Dwg System Safety OM Normal Safety Description Flow Diagram S t Coord Class Cat. Position Position I CS-341 RCP "A" Seal Water Injection Iso Vlv 2165-S-1303 K-3 2060 2 A 0 0/C (CIV)

I CS-382 RCP "B" Seal Water Injection Iso Vlv 2165-S-1303 SOI L-3 2060 2 A 0 0/C (CIV)

ICS-423 RCP "C" Seal Water Injection Iso Vlv 2165-S-1303 S02 K-3 2060 2 A 0 0/C (CIV)

I CS-470 RCP Seal Water Return & Excess LTDN 2165-S-1303 D-16 2060 2 A 0 (CIV)

I CS-472 RCP Seal Water Return & Excess LTDN 2165-S-1303 D-17 2060 2 A 0 (CIV)

Code Test Requirements Active Category A valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.2.1.

Deferred Test Justification Normally open, exercising these valves closed quarterly during normal operation would require interrupting seal water flow to the RCP shaft seals. The interruption of seal water flow to the RCP shaA seals is not practical during power operation due to the potential of causing damage to the seals. Exercising these valves closed during cold shutdowns, ifthe RCS were t

pressurized, or filled above the seal package level, could allow the RCS to flow through the pump seals. This flow could introduce particulates suspended in the RCS into the pump seals which would accelerate seal wear potentially resulting in premature failure. Testing these valves at refueling outages when the RCS drained to a level below the RCP seal packages would preclude damage to the seals.

Alternate Test (STC) Stroke time close at (RO) refueling outage (ref. OM-10, para. 4.2.1.2(e)

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 Valve Refueling Outage Justifications CS-ROJ5 Component Dwg Safety OM Normal Safety Description Flow Diagram Coord Class Cat. PositioJi Position I CS-348 RCP "A" Seal Water Injection Check 2165-S-1303 J-3 2060 I C 0 0/C I CS-349 RCP "A" Seal Water Injection Check 2165-S-1303 1-3 2060 I C 0 0/C I CS-389 RCP "B" Seal Water Injection Check 2165-S-1303 SO I J-3 2060 I C 0 0/C I CS-390 RCP "B" Seal Water Injection Check 2165-S-1303 SOI 1-3 2060 I C 0 0/C I CS-430 RCP "C" Seal Water Injection Check 2165-S-1303 S02 J-3 2060 I C 0 0/C I CS-431 RCP "C" Seal Water Injection Check 2165-S-1303 S02 1-3 2060 I C 0 0/C Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM-IO, Para. 4.3.2.

Deferred Test Justification These simple check valves are the Class I to 2 class boundary isolation check valves located inside the missle barrier inside primary containment. The valves are not provided with position indication nor are they provided with individual test connections. The installed test connections are located on either side of the pair of checks, but not between. The only method available to verify reverse flow closure capability of these check valves with fiow is as a pair. The only viable method to verify individual closure is by non-intrusive techniques. This technique (RT) requires the installation of test equipment and isolation of the area during the process. This method would require containment entry and the interruption of the valves'ormal process functions in order to verify their closure capability. Routine containment entry cannot be made quarterly during power operation due to high radiation levels and the potentially harsh environment inside primary containment. Plant procedures indicate that it is desireable to operate the pumps during cold shutdown and that at least one RCP be operating when RSC temperature is > 160 degrees F. Perfortning this test activity during cold shutdowns is not desirable due to personnel hazards and ALARAconcerns and the requirement to shut down and restart the reactor coolant pumps (RCP)'s.

Alternate Test (SC) Stroke close at (RO) refueling outage (ref. OM-10, para. 4.3.2.2(e)

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 Valve Refueling Outage Justifications CS-ROJ6 Component Flow Diagram Dwg System Safety OM Normal Safety Description S Coord Class Cat. Position Position I CSA93 RCS Normal Charging Isolation Valve 2165-S-1303 CA 2060 2 C 0 0 Bypass ICS-774 RCS Normal Charging Isolation Valve 2165-S-1303 C-5 2060 2 C 0 0 Bypass Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.3.2.

Deferred Test Justification These check valves provide thermal overpressure protection for the regenerative heat exchanger when it is isolated. Valve I CS-774 is spring loaded to restrict opening during normal operation, otherwise the valves are both simple check valves.

These normally closed valves are located inside the reactor containment. During power operation, this portion of the system is pressurized by normal charging. Testing these valves would require isolation of the normal, alternate charging, and pressurizer spray flow paths. Due to system configuration and location of test connections, the only method to verify closure would require a containment entry and installation of test equipment. Testing during normal operation is not practicable due to ALARAconcerns. Testing during cold shutdown is not practicable due to the need to setup test equipment.

NUREG-1482, Section 4.1.4 states, "... The NRC has determined that the need to setup test equipment is adequate justification to defer backflow testing until a refueling outage...".

1 Alternate Test (SO) Stroke open at (RO) refueling outage (ref. OM-10, para. 4.3.2.2(e)

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 Valve Refueling Outage Justifications CS-ROJ7 Component Dwg System Safety OM Normal Safety Description Flow Diagram $ t ID Coord Class Cat. Position Position I CS-525 Boric Acid Gravity Feed Line Check Vlv 2165-S-1307 E-7 2060 3 C C 0 I CS-526 Boric Acid Gravity Feed Line Manual 2165-S-1307 E-10 2060 2 B C 0/C Isolation Vlv Code Test Requirements Active Category B, and C check valves shall be exercised nominally every 3 months per the requirements of OM-10, Para.

4.2.1 and 4.3.2 respectively.

Deferred Test Justification These normally closed system isolation valves are located in the boric acid gravity feed line to the charging/safety injection pumps and may be used to supply water directly from the Boric Acid Tank to the suction of the CSIPs via gravity feed, if the Boric Acid Pumps are not operable. This flow path is optionally required to be operable per T.S.3.1.2.1 in Modes 4, 5 and 6.

Opening manual isolation valve ICS-526 during normal operation would negate redundent isolation between charging pump suction and boric acid subsystem. In addition, the boric acid subsystem pressure is not sufficient to open check valve I CS-525 during normal and cold shutdown operation because normal charging pump suction prcssure is greater than boric acid tank head pressure.

Alternate Test I CS-525 (SO) Stroke open at (RO) refueling outage (ref. OM-10, para. 4.3.2.2(e)

I CS-526 (SO) Stroke open at (RO) refueling outage (ref. OM-10, para. 4.2.1.2(e)

I CS-526 (SC) Stroke close at (RO) refueling outage (ref. OM- IO, para. 4.2.1.2(e)

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 Valve Refueling Outage JustiTications CS-ROJS Component Dwg Safety OM Normal Safety Description Flow Diagram System ID Coord Class Cat. Position Position I CS-483 RCS Alternate Charging Line Check Vlv 2165-S-1303 B-3 2060 C 0/C I CS-486 RCS Alternate Charging Line Check Vlv 2165-S-1303 B-3 2060 0/C I CS-488 Pressurizer Auxiliary Spray Line 2165-S-1303 C-3 2060 C Injection Check Vlv I CS-491 Pressurizer Auxiliary Spray Line 2165-S-1303 C-3 2060 I C C C Injection Check Vlv I CS-497 RCS Normal Charging Line Check Vlv 2165-S-1303 C-3 2060 I C 0 0/C ICS-500 RCS Normal Charging Line Check Vlv 2165-S-1303 B-3 2060 I C 0 0/C Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.3.2.

Deferred Test Justiflcation These simple check valves are the Class I to 2 class boundary isolation check valves located inside the missle barrier inside primary containment. During power operation, this portion of the system is pressurized by normal charging. Testing these valves would require isolation of the normal, alternate charging, and pressurizer spray flow paths. Due to system configuration and location of test connections, the only method to verify closure would require a containment entry and installation of test equipment. Testing during normal operation is not practicable due to ALARAconcerns. Testing during cold shutdown is not practicable due to the need to setup test equipment.

NUREG-I482, Section 4.1.4 states, "... The NRC has determined that the need to setup test equipment is adequate justification to defer backflow testing until a refueling outage...".

Alternate Test Revision 0 Page 132 of 145

HNP-IST-002 HNP IST Program'Plan - 2nd Inteval 5.6 Valve Refueling Outage Justifications CT-ROJl Component Dwg System Safety OM Normal Safety Description Flow Diagram S ID Coord Class Cat. Position Position ICT-53 Containment Spray Pump "A" Disch to 2165-S-550 F-3 2070 2 A/C C 0/C Nozzles Check Vlv (CIV)

ICT-91 Containment Spray Pump "B" Disch to 2165-S-550 K-3 2070 2 A/C C 0/C Nozzles Check Vlv (CIV)

Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM- IO, Para. 4.3.2.

Deferred Test Justification Normally closed, these check valves are located inside primary containment serving as inboard containment isolation valves and are not provided with position indication. The only method available to verify reverse flow closure capability of these check valves is to perform a seat leakage test. The test connections utilized to perform seat leakage testing are located inside containment. Therefore, it would require containment entry in order to verify valve closure. Routine containment entry cannot be made quarterly during power operation due to high radiation levels and the potentially harsh environment inside primary containment.

NUREG-1482, Section 4.1.4 states, "... The NRC has determined that the need to setup test equipment is adequate justification to defer backflow testing until a refueling outage...".

Alternate Test (SC) Stroke close at (RO) refueling outage during Appendix J, Type C, testing (ref. OM- IO, para. 4.3.2.2(e) and Section 4.1.4 of USNRC NUREG-1482)

(SO) Stroke open testing is (SDIS) per Relief Request CT-VRI Revision 0 Page 133 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Intcval 5.6 Valve Refueling Outage Justifications DW-ROJ1 Component Flow Diagram Dwg System Safety OM Normal Safety ID Coord Class Cat. Position Position 1DW-65 Demin Water Supply to Primary Cont 2165-S-799 H-6 6270 2 A/C C 0/C (CIV)

Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.3.2.

Deferred Test Justiflcation Normally closed, this check valve is located inside primary containment serving as an inboard containment isolation valve and is not provided with position indication. The only method available to verify reverse flow closure capability of this check valve is by seat leakage testing. The test connections utilized to perform seat leakage testing are located inside containment. Therefore, it would require containment entry in order to verify valve closure. Routine containment entry cannot be made quarterly during power operation due to high radiation levels and the potentially harsh environment inside primary containment.

NUREG-1482, Section 4.1.4 states, "... The NRC has determined that the need to setup test equipment is adequate justification to defer backflow testing until a refueling outage...".

Alternate Test (SO) Stroke open at (RO) refueling outage and (SC) Stroke close at (RO) refueling outage during Appendix J, Type C, testing (ref. OM-10, para. 4.3.2.2(e) and Section 4.1.4 of USNRC NUREG-1482)

Revision 0 Page 134 of 145

0 HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 Valve Refueling Outage Justifications FP-ROJ1 Component Dwg System Safety OM Normal Safety Description Flow Diagram S ID Coord Class Cat. Position Position I FP-349 Fire Water Sprinkler Supply Check Vlv 2165-S-888 L-3 6175 2 A/C C 0/C (CIV)

I FP-357 Fire Water Standpipe Supply Check Vlv 2165-S-888 L-3 6175 2 A/C C 0/C (CIV)

Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.3.2.

Deferred Test Justification Normally closed, these simple check valves are located inside primary containment serving as inboard containment isolation valves and are not provided with position indication. The only method available to verify reverse flow closure capability of these check valves is by seat leakage testing. The test connections utilized to perform seat leakage testing are located inside containment. Therefore, it would require containment entry in order to verify valve closure. Routine containment entry cannot be made quarterly during power operation due to high radiation levels and the potentially harsh environment inside primary containment.

NUREG-1482, Section 4.1.4 states, "... The NRC has determined that the need to setup test equipment is adequate justification to defer backflow testing until a refueling outage...".

Alternate Test (SO) Stroke open at (RO) refueling outage and (SC) Stroke close at (RO) refueling outage during Appendix J, Type C, testing (ref. OM-IO, para. 4.3.2.2(e) and Section 4.1.4 of USNRC NUREG-1482 Revision 0 Page 135 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 Valve Refueling Outage Justifications IA-ROJI Component Dwg System Safety OM Normal Safety Description Flow Diagram S Coord Class Cat. Position Position I IA-220 Instrument Air Supply to Containment 2165-S-801 D-12 6135 2 A/C 0 C Check Vlv (CIV)

Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM-IO, Para. 4.3.2.

Deferred Test Justification Normally open, this check valve is located inside primary containment serving as an inboard containment isolation valve and is not provided with position indication. The only method available to verify reverse flow closure capability of this check valve is by seat leakage testing. The test connections utilized to perform seat leakage testing are located inside containment. Therefore, it would require containment entry in order to verify valve closure. Routine containment entry cannot be made quarterly during power operation due to high radiation levels and the potentially harsh environment inside primary containment.

NUREG-1482, Section 4.1.4 states, "... The NRC has determined that the need to setup test equipment is adequate justification to defer backflow testing until a refueling outage...".

Alternate Test (SC) Stroke close at (RO) refueling outage during Appendix J, Type C, testing (ref. OM-10, para. 4.3.2.2(e) and Section 4.1.4 of USNRC NUREG-1482 Revision 0 Page 136 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Intcval 5.6 Valve Refueling Outage Justifications RC-ROJ1 Component Description Flow Diagram Dwg System 'Safety OM Normal Safety Coo rd Class Cat. Position Position 1RC-164 RMW to PRT Iso Vlv (CIV) 2165-S-1301 D-16 2050 2 A/C 0/C 0/C Code Test Rcquircments Check valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.3.2.

Deferred Test JustiTication Normally closed, this simple check valve is located inside primary containment serving as an inboard containment isolation and is not provided with position indication. The only method available to verify reverse flow closure capability of 'alve this check valve is by seat leakage testing. The test connections utilized to perform seat leakage testing are located inside containment. Therefore, it would require containment entry in order to verify valve closure. Routine containment entry cannot be made quarterly during power operation due to high radiation levels and the potentially harsh environment inside primary containment.

NUREG-1482, Section 4.1.4 states, "... The NRC has determined that the need to setup test equipment is adequate justification to defer backflow testing until a refueling outage...".

Altcrnatc Test (SC) Stroke close at (RO) refueling outage during Appendix J, Type C, testing (ref. OM- IO, para. 4.3.2.2(e) and Section 4.1 4 of USNRC NUREG-1482)

(SO) Stroke open verified (Q) quarterly Revision 0 Page 137 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 Valve Refueling Outage Justifications RC-ROJ2 Com p onent Co Dwg System Safety OM Normal Safety Description Flow D Fl Diagram S t ID Coord Class Cat. Position Position 1RC-174 N2 Inlet Check Vlv to PORV N2/Air 2165-S-1309 B-'9 2050 3 A/C 0/C C Accum. Tank I A-SA I RC-176 N2 Inlet Check Vlv to PORV N2/Air 2165-S-1309 A-9 2050 3 A/C 0/C Accum. Tank IC-SB ISI-444 Instr. Air Inlet Check Vlv to PORV 2165-S-1309 B-6 2050 3 A/C 0/C N2/Air Accum. Tank 1A-SA ISIP46 Instr. Air Inlet Check Vlv to PORV 2165-S-1309 A-6 2050 3 A/C 0/C N2/Air Accum. Tank I C-SB Code Test Requirements Check valves shall be exercised nominally every 3,months per the requirements of OM-10, Para. 4.3.2.

Deferred Test JustiTication Normally open/closed, these simple check valves are located in the normal instrument air and nitrogen supply lines to the actuating air accumulators serving the two safety related PORVs, both of which are inside primary containment. The valves are not provided with remote position indication. To verify reverse flow closure capability of these check valves would require isolating and the depressurization of the instrument air and nitrogen supply headers for an extended period of time, and performing an accumulator pressure decay test. This test activity would require containment entry in order to verify t

valve closure. Routine containment entry cannot be made quarterly during power operation due to high radiation levels and the potentially harsh environment inside primary containment. The reverse closure test is not practical during cold shutdowns since the PORVs are required to be available during cold shutdowns to prevent low temperature overpressunzat ion of the RCS.

Alternate Test (SC) Stroke close at (RO) refueling outage (ref. OM-10, para. 4.3.2.2(e)

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 Valve Refueling Outage Justifications SA-ROJ1 Component Dwg Safety OM Normal Safety Description Flow Diagram $ t System Coord Class Cat. Position Position I SA-82 Service Airto Containment (CIV) 2165-S-800 C-3 6140 2 A/C C C Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.3.2.

Deferred Test Justification Normally closed, this check valve is located inside primary containment serving as an inboard containment isolation valve and is not provided with position indication. The only method available to verify reverse flow closure capability of this check valve is by seat leakage testing. The test connections utilized to perform seat leakage testing are located inside containment. Therefore, it would require containment entry in order to verify valve closure. Routine containment entry cannot be made quarterly during power operation due to high radiation levels and the potentially harsh environment inside primary containment.

NUREG-1482, Section 4.1.4 states, "... The NRC has determined that the need to setup test equipment is adequate justification to defer backflow testing until a refueling outage...".

Alternate Test (SC) Stroke close at (RO) refueling outage during Appendix J, Type C, testing (ref. OM-10, para. 4.3.2.2(e) and Section 4.1A of USNRC NUREG-1482 Revision 0 Page 139 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 Valve Refueling Outage Justifications SI-ROJ1 ComPonent Dwg System Safety OM Normal Safety Des<<lpt<<n Flow Diagram S ID Coord Class Cat. Position Position ISI-IO RCS Cold Leg Loop 3 Inj Ck Vlv (CIV) 2165-S-1308 E-5 2080 I C C 0/C I SI-104 RCS Hot Leg Loop I Inj Ck Vlv (CIV) 2165-S-1308 E-12 2080 I C C 0/C IS1-105 RCS Hot Leg Loop 2 Inj Ck Vlv (CIV) 2165-S-1308 E-13 2080 I C C 0/C ISI-106 RCS Hot Leg Loop 3 Inj Ck Vlv (CIV) 2165-S-1308 E-14 2080 I C C 0/C I SI-127 RCS Hot Leg Loop I Inj Ck Vlv (CIV) 2165-S-1308 E-15 2080 I C C 0/C I SI-128 RCS Hot Leg Loop 2 Inj Ck Vlv (CIV) 2165-S-1308 E-16 2080 I C C 0/C I SI-129 RCS Hot Leg Loop 3 Injn Ck Vlv (CIV) 2165-S-1308 E 17 2080 I C C 0/C ISI-138 ISI-72 RCS Hot Leg Loop 3 Inj Ck Vlv RCS Cold Leg Loop I Alt. Inj Ck Vlv (CIV) 2165-S-1308 2165-S-1308 D-17 E-6 2080 2080 I

I C

C C

C '/C 0/C I SI-73 RCS Cold Leg Loop 2 Alt. Inj Ck Vlv 2165-S-1308 E-7 2080 I C C 0/C (CIV)

ISI-74 RCS Cold Leg Loop 3 Alt. Inj Ck Vlv 2165-S-1308 E-8 2080 I C C 0/C (CIV)

I SI-8 RCS Cold Leg Loop I Inj Ck Vlv (CIV) 2165-S-1308 E-3 2080 C C 0/C I SI-9 RCS Cold Leg Loop 2 Inj Ck Vlv (CIV) 2165-S-1308 E-4 2080 I C C 0/C Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM-IO, Para. 4.3.2.

Deferred Test Justification Normally closed, full stroke exercising open can only be performed by injecting water into the RCS utilizing the RWST as the supply source. Design accident injection flow rate cannot be established through these valves when the reactor coolant system is at normal operating pressure. The normal operating pressure of the RCS would prevent the flow rates that can be achieved when the RCS is depressurized, as it would be in the case of a large break LOCA. Therefore, these valves cannot be full-stroke exercised open quarterly during power operations. Partial-stroke exercising these valves during power operations would inject cold water, which has bypassed the regenerative heat exchanger, into the RCS thermally shocking the injection piping and nozzles which could cause premature failure of these system components. Also, establishing injection flow into the RCS could cause reactivity, temperature, pressure, and pressurizer level control transients which could result in a reactor trip. Exercising these valves during cold shutdowns when the RCS is not vented or open to the atmosphere would inject into the RCS when there is marginal expansion volume and could result in low-temperature overpressurization of the RCS Alternate Test (SO) Stroke open at (RO) refueling outage (SC) Stroke close at (RO) refueling outage (ref. OM- 10, para. 4.3.2.2(e))

Revision 0 Page 140 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 Valve Refueling Outage Justifications SI-ROJ2 Component Dvvg Safety OM Normal Safety Description Flow Diagram System S

Coord Class Cat. Position Position ISI-I07 Alternate High Head SI to Hot Leg (CIV) 2165-S-1308 H-15 2080 2 B C 0/C I SI-52 Alternate High Head SI to Cold Leg 2165-S-1308 H-10 2080 2 B C 0/C (CIV)

High Head SI to Hot Leg (CIV) 2165-S-1308 H-12 2080 2 B C 0/C Code Test Requirements Active Category B valves shall be exercised nominally every 3 months per the requirements of OM-IO, Para. 4.2.1.

Dcfcrrcd Test Justification Normally closed, full stroke exercise open of these valves during power operation would result in flow through the injection flow paths into the RCS hot legs when I SI-86 and 107 are opened, and into the RCS cold legs when SI-52 is opened. Aligning this flow path would allow the injection of relatively cold water, which has bypassed the regenerative heat exchanger, into the RCS potentially thermal shocking the injection piping and nozzles which could cause premature failure of these system components. Opening these valves would also allow an increase in charging/injection flow potentially causing reactivity, temperature, pressure, and pressurizer level control transients which could result in a reactor trip. At cold shutdown one charging pump remains in service per T.S. 3.5.3 when RCS temperature is <335 degrees F.

Exercising these valves to the open position during cold shutdown would allow substantial increased flow into the RCS when there is marginal expansion volume to accommodate the additional flow for the test period. This increased flow could cause a low temperature overpressure condition in the RCS. The control circuitry associated with this valve is not provided with partial stroke capability. Even ifpossible, partial stroke exercising would result in the same consequences as full exercising.

Alternate Test (STO) Stroke time open at (RO) refueling outage (STC) Stroke time closed at (RO) refueling outage (ref. OM- IO,.para. 4.2.1.2(e Revision 0 Page 141 of 145

HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 Valve Refueling Outage Justifications SI-ROJ3 Com onent Compo Flow Diagram Dwg System Safety OM Normal Safety Description ID Coord Class Cat. Position Position I SI-182 Accumulator Fill from RWST (CIV) 2165-S-1309 J-16 2090 2 A/C 0/C 0/C I SI-290 Accumulators 0, Prz PORV N2 Supply 2165-S-1309 B-17 2090 2 A/C 0/C C Check Vlv (CIV)

Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM- IO, Para. 4.3.2.

Deferred Test JustiTication Normally open/closed, these check valves are located inside primary containment serving as inboard containment isolation valves and are not provided with position indication. The only method available to verify reverse flow closure capability of these check valves is by seat leakage testing. The test connections utilized to perform seat leakage testing are located inside containment. Therefore, it would require containment entry in order to verify their closure capability. Routine containment entry cannot be made quarterly during power operation due to high radiation levels and the potentially harsh environment inside primary containment.

NUREG-1482, Section 4.1.4 states, "... The NRC has determined that the need to setup test equipment is adequate justification to defer backflow testing until a refueling outage...".

Alternate Test (SC) Stroke close at (RO) refueling outage during Appendix J, Type C, testing (ref. OM-IO, para. 4.3.2.2(e) and Section 4.1.4 of USNRC NUREG-1482)

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l HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 Valve Refueling Outage JustiTications SI-ROJ4 Component Dwg System Safety OM Normal Safety Description Flow Diagram S t ID Coord Class Cat. Position Position I SI-320 RHR Pump "A" Suction Supply Check 2165-S-13 10 N-12 2080 2 C C 0/C Vlv. from RWST I SI-321 RHR Pump "B" Suction Supply Check 2165-S-13 10 M-12 2080 2 C C 0/C Vlv. from RWST Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM-IO, Para. 4.3.2.

Deferred Test Justification These valves are normally closed. A proper backseat test involves pressurization of the piping downstream of each check valve by a high capacity external pressure source. Pressurization from the opposite safety train is not possible due to check valves on the pump discharge line upstream of the nearest crossover line. These discharge check valves would potentially mask a non-functional suction check valve. Performing this test during cold shutdown is considered burdensome without a commensurate increase in the level of valve reliability due to the necessity of utilizing temporary test equipment and the extent of the test boundary which could delay plant restart. Additionally, this test activity could impact the ability to maintain the plant at cold shutdown under normal conditions due to the necessity of having one train of RHR operating in the shutdown cooling mode. The only time that a high volume pressurization source to these valves exists, without impacting system operation, is during refueling outages when the refueling cavity is flooded and the plant is lined up on residual heat removal.

At this time the static head from the refueling cavity will exceed that of the RWST thereby providing a reverse differential pressure across ISI-320 and ISI-321. Monitoring of RWST level over a specified period of time will provide adequate demonstration of reverse flow closure capability.

Alternate Test (SC) Stroke closed at (RO) refueling outage (ref. OM-10, para. 4.3.2.2(e)

(SO) Stroke open is verified (Q) quarterl Revision 0 Page 143 of 145

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HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 'alve Refueling Outage Justifications SI-ROJ5 Component Dwg Safety OM Normal Safety Description Flow Diagram System Coord Class Cat. Position Position ISI-134 SI Low Head to RCS Hot Leg Loops I 2165-S-1308 B-11 2080 I A/C C 0/C (CIV) (PIV)

IS1-135 SI Low Head to RCS Hot Leg Loop2 2165-S-1308 C-11 2080 I A/C C 0/C (CIV) (PIV)

ISI-136 RCS Hot Leg Loop I Inj Ck Vlv 2165-S-1308 B-17 2080 C C 0/C IS1-137 RCS Hot Leg Loop 2 Inj Ck Vlv 2165-S-1308 C-17 2080 I C C 0/C I SI-346 LHSI Train "A" to Cold Legs Inj. Check 2165-S-1310 C-3 2080 2 A/C C 0/C (PIV/CIV)

I SI-347 LHSI Train "B" to Cold Legs Inj. Check 2165-S-1310 E-3 2080 2 A/C C 0/C (PIV/CIV)

I SI-356 LHSI to RCS Cold Leg Loop I (PIV) 2165-S-1310 C-2 2080 I A/C C 0/C ISI-357 LHSI to RCS Cold Leg Loop 2 (PIV) 2165-S-1310 E-2 2080 I A/C C 0/C I SI-358 LHSI to RCS Cold Leg Loop 3 (PIV) 2165-S-1310 E-2 2080 I A/C C 0/C I SI-81 RCS Cold Leg Loop I Injection Check 2165-S-1308 B-3 2080 C C 0/C I SI-82 RCS Cold Leg Loop 2 Injection Check 2165-S-1308 C-3 2080 I C C 0/C ISI-83 RCSCold Leg Loop3 Injection Check 2165-S-1308 D-3 2080 I C C 0/C Code Test Requirements Check valves shall be exercised nominally every 3 months per thc requirements of OM-10, Para. 4.3.2.

Dcferrcd Test JustiTication These normally closed valves are located inside the reactor containment. During power operation, this portion of the system is pressurized to reactor pressure. No installed plant instrumentation exists to validate or monitor inservice conditions. Due to system configuration and location of test connections, the only method to verify closure would require a containment entry and installation of test equipment. The installation of test equipment would require breaching the isolation requirements for the reactor coolant pressure boundary. Testing during normal operation is not practicable due to ALARA concerns. Testing during cold shutdown is not practicable due to thc need to setup test equipment.

Reference NUREG-1482, Section 4.1.4 states, "... The NRC has determined that the need to setup test equipment is adequate justification to defer backflow testing until a refueling outage...".

Alternate Test (SC) Stroke close at (RO) refueling outage (ref. OM-IO, para. 4.3.2.2(e)

(SO) Stroke open is per Sl-CSJI Revision 0 Page 144 of 145

0 HNP-IST-002 HNP IST Program Plan - 2nd Inteval 5.6 Valve Refueling Outage Justifications SW-ROJ1 Component Dwg System Safety OM Normal Safety Description Flow Diagram S ID Coord Class Cat. Position Position 1SW-233 SW Supply to Containment Fan Coil 2165-S-547 C-15 4060 2 A/C 0 0/C Units Check Vlv (CIV)

Code Test Requirements Check valves shall be exercised nominally every 3 months per the requirements of OM-10, Para. 4.3.2.

Deferred Test Justification Normally open, this simple check valve is located inside primary containment serving as an inboard containment isolation valve and is not provided with position indication. The only method available to verify reverse flow closure capability of this check valve is to stop normal service water flow to primary containment and perform a seat leakage test. The test connections utilized to perform seat leakage testing are located inside containment. Therefore, it would require containment entry in order to verify valve closure. Routine containment entry cannot be made quarterly during power operation due to high radiation levels and the potentially harsh environment inside primary containment.

NUREG-1482, Section 4.1.4 states, "... The NRC has determined that the need to setup test equipment is adequate justification to defer backflow testing until a refueling outage...".

Alternate Test (SC) Stroke close at (RO) refueling outage during Appendix J, Type C, testing (ref. OM-10, para. 4.3.2.2(e) and Section 4.1.4 of USNRC NUREG-1482)

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