ML20082L701

Inservice Insp Program Plan for 1980-1983 Period

ML20082L701
Person / Time
Site:	Fort Calhoun
Issue date:	08/31/1983
From:	OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20082L679	List: ML20082L669 ML20082L701
References
PROC-830831, NUDOCS 8312050562
Download: ML20082L701 (55)

Text

Attachaent 2 1-Omaha Public Power District Fort Calhoun Station Unit No.1 Inservice Inspection Program Plan for the 1980-1983 Period Revisions:

March, 1977 August, 1977 February, 1978 September, 1978 August, 1982 August, 1983 8312050562 830926 PDR ADOCK 05000285 G PDR

Program Table of Contents Page

-INTRODUCTION: Discussion PART 1: Class 1, 2, and 3 Pressure Retaining Components 1 Program: ICI-1.1.0 Scope and Responsibility 1 101-1.2.0 Inspection Intervals 1 ICI-1.3.0 Examination Categories 1 1C1-1.4.0 Examination Methods 2 1C1-1.5.0 Evaluation of Examination Results 2

, 101-1.6.0 Repair Requirements 3

~ICI-1.7.0 System Pressure Testing 4 101-1.8.0 Records and Reports 4 Appendix 1A Piping and Instrumentation Drawings 7 Appendix 1B Exceptions to Compliance with Table IWB-2600 8 Appendix 1C Exceptions to Compliance with Table IWC-2600 11 Appendix 1D Exceptions to Compliance with Article IWD-2000 12 PART 2: Class 1, 2, and 3 Pump and Valve Tests 13 Program: ICI-2.1.0 Scope and Responsibility 13

. ICI-2.2.0 Inspection Intervals 13 101-2.3.0 Examination Categories 13 1C1-2.4.0 Examination Methods 13 ICI-2.5.0 Evaluation of Examination Results 13 ICI-2.6.0 Records and Reports 14 ICI-2.7.0 Repair Requirements 14 Appendix 2A Inservice Inspection of Pumps 15-19 Appendix 2B Inservice Inspection of Valves 20-38 Table 2B-1 21 Appendix 2C Function of Valves to which Test 39-46 Exceptions are Requested Appendix 3 Abbreviations, Definitions and Clarifications 47

References:

48 Table 1.1 Class 1 Components, Parts, and Method of Examination 49-51 Table 1.2 Class 2 Components, Parts and Method of Examination 52 i

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Introduction:

This report defines the Inservice Inspection Program for Class 1, 2, and 3 pressure retaining components for the period starting May 26, 1980 to September 26, 1983 and Class 1, 2, and 3 pumps and valve testing for period starting September 26, 1978 to September 26, 1983.

This program has been developed as required by Sec. 50.55 (a) of 10 CFR Part 50 following the guidance of the ASME Boiler Pressure Vessel Code Section XI,

" Rules for Inservice Inspection of Nuclear Power Plant Components". The ISI program (Inservice Inspection) will be controlled by the Fort Calhoun Station Unit No. 1. Technical Specifications.

This Inservice Inspection program is in compliance where possible, with the applicable requirements of Section XI,1974 (Summer 1975 Addenda) of the ASME B and PV Code.

This program incorporates the results of previous inservice and pre-service inspections. It is the intent of the Licensee to continue to review and apply, as appropriate, changes in the code which would improve the total Inservice Inspection Program, pursuant to 10 CFR 50.55(a).

Part 1: Class 1, 2 and 3 Pressure Retaining Components 1.1 Scope and Responsibility 1.1.1 The Piping and Instrument Drawings (P and ID's) in Appendix 1A identify the boundaries are always under review and are subject to change.

1.1.2 Class 1 and Class 2 components and the methods of examination for each component are listed in Tables 1.1 and 1.2, respectively. Class 3 components are those found on the P and ID's in Appendix 1A. The specific components to be examined for each class shall be identified in the Fort Calhoun Station Unit No. 1 Inservice Examination Plan by title and/or number. Class 3 components will be examined to the extent required by IWD-2600. Exceptions to com with Tables IWB-2600 and IWC-2600 of Reference are (1) pliance listed in Appendix 18 and Appendix 1C, respectively.

1.2 Inspection Intervals 1.2.1 The inspection intervals for class 1, 2, and 3 components will be ten-year intervals of service commencing on September 26, 1973. As indicated previously, this copy of the program plan covers the first ten year intervals, i.e., September 26, 1973 to September 26, 1983.

Ten year examination plans will describe the distribution of examination within the inspection intervals in accordance with IWB-2400, IWC-2400, and IWD-2400 of Reference (1).

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1.2.2 Thc inspection intervals for classes 1, 2, and 3 components may be extended by as much as one year to permit inspections to be concurrent with plant outages as pennitted by IWA-2400 of reference (1).

1.3 Examination Catagories 1.3.1 Class 1 components as listed herein in Table 1, will be examined to the extent and frequency as required by Table IWB-2500 of Reference (1). Note: As a result of the 1980 Inservice Inspection the District has adopted a policy of examining the Reactor Coolant Pump Casing Studs every refueling outage. This policy will be pursued rather than the code required "once per interval" inspection.

1.3.2 Class 2 components as listed herein in Table 2 will be examined to the extent and frequency as required by Table IWC-2500 of Reference (1).

1.3.3 Class 3 components as described in the ten year examination plan shall be examined to the extent and frequency as re-quired by Table IHD-2600 and IWD-2400 of reference (1).

Open- ended portion of a system extending to the first shutoff valve and buried system components shall be exempted from pressure test and from inspection where accessibility is restricted.

1.4 Examination Methods 4

1.4.1 Class 1 and 2 components shall be examined by the required visual, surface and volumetric examinations. These examinations shall include one or a combination of the l

following methods: visual, (VT), liquid penetrant, (PT) j magnetic particle, (MT), and radiographic examination in accordance with IWA-2200 of Reference (1). Ultrasonic examinations shall be performed in accordance with the following:

1.4.1.1 Ultrasonic examination of ferritic vessels with a wall thickness of 21/2 inches or greater shall be conducted in accordance with Appendix I of Reference (1).

1.4.1.2 Ultrasonic examinations of piping welds shall be conducted in accordance with article 5 of Re-ference (2) with the following exceptions: All ultrasonic indications which produce a response i greater than 50% of the reference level will be recorded, and all indications which produce a response greater than 100% of the reference level i will be investigated and evaluated in accordance I

with Paragraph IWA-2232 of the Summer 1976 Addenda j

l to Section XI. Indications of 20% of the reference

1~.4.1.2 (Continued) level or greater which are interpreted to be a crack shall be identified and evaluated to the rules of Section IX. The ultrasonic examination of ferritic piping will be performed in accordance with the

. procedural requirements of Appendix I to the Summer 1975 addenda, ASME,Section XI.

1.4.1.3 The volumetric examinations of Class 2 circum-ferential pipe welds will conform to the addi-tional examination requirements of IE Circular 76-06, dated November 24, 1976 in that the examined area shall, where possible, cover a distance of approximately six times the pipe wall

thickness (but not less than two inches and not to exceed 8 inches) on each side of the weld. This additional examination area shall apply only to SI and CS systems piping.

1.4.2 Class 3 components shall be visually examined for leakage in accordance with Article IWD-2000 of Reference (1).

1.5 Evaluation of Examination Results

' 1.5.1 Class 1 Components 1.5.1.1 The evaluation of the non-destructive examination results shall be in accordance with Article IWB-3000 of Reference (1). All indications shall be subject to comparison with previous data to help in characterization and in determining origin. ,

1.5.2 Class 2 Components 1.5.2.1 The evaluation of nondestructive examination results shall be in accordance with Article IWB-3000 of Reference (1). All indication shall be subject to comparison with previous data to help in characterization and in determining origin.

1.5.3 Class 3 Components 1.5.3.1 The evaluation of the visual examination results

' shall be in accordance with Article IWA-5000 of Reference (1).

1.5.4 Indications which have been recorded in the Preservices inspection or in a previous Inservice Inspection which are not characterized as propagating flaws shall be accepted for 1

continued service.

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1.6 Repair Requirements 1.6.1 Repair of Class 1, 2 and 3 components shall be perfonned in accordance with Article IWA-4000 of Reference (1).

1.6.2 Surface defects in class 1, 2 and 3 bolts, studs, nuts and ligaments may be removed by mechanical means when the re-moval of a defect will not alter the basic configurations of the item. Bcits, studs and nuts that have defects that cannot be removed by mechanical means shall be replaced.

1.7 System Pressure Testing 1.7.1 General Requirements:

1.7.1.1 System Pressure test will be conducted in accord-ance with Article IWA-5000 of Reference (1).

1.7.1.2 Evaluation of any corroded area will be performed in accordance with Article IWA-5000 of Reference (1).

1.7.1.3 Repairs of corroded areas shall be performed in accordance with Section 1.6 of this program.

1.7.2 Class 1 Components 1.7.2.1 Whenever the reactor coolant system is closed after it has been opened, the system will be leak tested in accordance with Article IWA-5000 and Article IWB-5000 of reference (1) and accordance with Fig. 2-1 and 2-2 of the Technical Specifi-cations.

1.7.2.2 At or near the end of each inspection interval, a hydrostatic pressure test shall be performed on the reactor coolant system components. This test i shall be conducted in accordance with the require-ments of Article INA-5000 and IWB-5000 of Reference (1). Test temperature shall be in l

accordance with Figures 2-1 and 2-2 of the Technical Specifications.

1.7.3 Class 2 Components 1.7.3.1 Pressure tests and visual examination of class 2 l components will be performed in accordance with the guidelines of paragraph IWC-2412 of Reference (1). The test pressure will be in accordance with the requirements of Article IWC-5000, Winter 1977 Addenda, in exception to the requirements of Reference (1). The Technical Specification 2.1.1, limiting the number of cylces at 125% of design pressure to 10 for the seconAry system (steam /

feedwater) will be taken into consideration.

Exemption from Temperature Requirements:

Basis for Exception:

The majority of the Class 2 piping systems, subject to the Section XI pressure testing, can be tested only when the plant is in a cold shutdown condition. While in this mode, there does not exist a means of heating the piping systems above ambient temperatures. Providing a means of heating long piping systems to 100 F is considered imprac-tical, within the meaning of 10 CFR 50.55a.

The minimum temperature requirement for performing a system hydrostatic pressure test was established to meet the requirements specified by fracture prevent criteria. Since the Fort Calhoun ferritic components' ambient room temperatures are sufficiently above brittle fracture tempera-tures (NDT typically -20 F), heating the systems to 100 F is unneces-sary. For the austenitic steel components, the NDT temperature is typically -325*F; far below any possible testing temperature. Again, heating the austenitic materials to 100 F is unnecessary.

Preservice hydrostatic tests were performed at ambient temperatures and it is the judgment of OPPD that hydrotesting at ambient temperatures is still acceptable.

Exemption on Safety Injection and Containment Spray Discharge Piping With Respect to Hydro Test Pressures.

Basis for Exception:

A In order to test the discharge piping of the Safety Injection and A Containment Spray pumps, the suction piping and the pumps must be A

pressurized to the pressure set by the discharge, or the pumps A removed from the system and re-installed after the test. A Evaluations by the District Generation Station Engineering has A indicated that pressurization of the suction piping of the HPSI A pumps is not allowed at the required elevated pressure.

A The suction and discharge lines could be separated by means of a A pancake between the flange faces on either the suction or discharge A of the pumps. However, this would require the removal of the pump A from the system. Removal and replacement of the pumps would require A an estimated 168 man hours per pump, resulting in an estimated 1.68 A man Rem per pump exposure.

A The 1980 addition of the ASME Section XI code, Article IWA-5224 (d) A states, "Where the respective system primary ratings on the suction and A discharge side of the system pumps differ, the system test boundary A shall be divided into two separate boundaries (such as suction side and discharge side test boundaries). In the case of positive A

A displacement pumps the boundary interface shall be the first shutoff A valve on the discharge side."

On these basis, the District requests exemption from the 1974/75 A summer Addenda Section XI requirements for these lines. This A would include the discharge piping between the pump and discharge A check valve of all safety injection pumps and containment spray A pumps, including the minimum recirculation line which returns to A the Safety Injection Refueling Water Tank (SIRWT). This exemption A seeks to lower the hydro test pressure required for these A components by following the 1980 Section XI requirements. A 1.7.4 Class 3 components 1.7.4.1 Class 3 components shall be pressure tested in accordance with article IWD-5000 of Reference (1).

1.8 Records and Reports Records and reports for this inspection made in accordance with this program shall be developed and maintained in accordance with Article IWA-6000 of Reference (1).

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l APPEllDIX 1A i The applicable Piping and Instrumentation Drawings accompany this report. .l i

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r APPENDIX 1B EXCEPTIONS TO COMPLIANCE WITH TABLE IWB 2600 (CLASS 1 COMPONENTS) IN ASME B0ILER AND PRESSURE VESSEL CODE, SECTION XI, SUMMER 1975 ADDENDA NOTE: Exemptions to be added to the Program Plan, to reflect P.P. examinations which were not accomplished during the 1983 ISI,nor previously. -

Item No. Exception B 1.2 The meridional and circumferential seam welds in the closure A head can not be examined due to interference from the A Seismic Skirt and Control Rod Drive housings. (Even if the A examiners could access these areas, the radiation level is A high enough to use up a vendor's complete quarterly A allowance doing a single customer's exam. For this reason A alone, the District would have trouble doing these exams.) A Therefore, exemption is requested, to allow the District to A test these welds by IWA-5000. A B 1.2 None of the Meridional welds on the lower heed were acces- A sible due to interference from the internal supports and A flow skirt. Therefore exemption is reauested to allow the A District to test these welds by IWA-5000. A B 1.3 The Closure Head to Flange weld can not be subject to A examination due to the interference the seismic skirt A presented. Therefore, and exemption is requested, to allow A the District to test these welds by IWA-5000. A B 1.4 The nozzle-to vessel welds cannot be 100% volumetrically examined from the 0.D. since the nozzle supports present an interference to currently available equipment. The nozzle-to-vessel welds will be examined during the Reactor Vessel Examination at the end of the interval, This examination will be from the I.D.

Bl.6 The nozzel to safe end welds can only be examined to 270 A of 360' due to the interference of the vessel supports and A insulation. The volumeteric examination of these welds was A performed 100% during the 1983 outage, from the I.D., A (rather than 331/3% every 3 years), as allowed by IWB-2500 A and Table B-0 of table IWB-2500. Because the I. D type A Volumetric exam is very good at detecting flaws near the A O.D. of a subject pipe. and since part of the rationale for A doing the 0.D. surface (P.T.) exam was to catch surface A cracks that an 0. D. Ultrasonic exam night miss, the A District feels that the I. D. volumetric and the 270 P.T. A are more than adequate for this weld. A Appendix 1B (Continued)

Item No. Exception B 1.7-1.8 The volumetric total examined of closure studs may be limited per ASME code case N-307, according to NRC letter of October 8,1981, Clark to Jones (and attached SER).

The control Rod Drive housings exams were not performed due to the same interferences that blocked the B1.2 B-B exams.

Exemption requested to allow examination by IWA-5000.

B 2.2 The nozzle-to-shell weld and the inside radiused section of the surge line connection cannot be completely inspected volumetrically due to interference from the heater penetra-tions. The weld and inside radiused section will be exam-ined volumetrically to the extent possible and according to the schedule designated in the Examination Plan.

B 2.5, 2.6, 2.7 These items are deleted in the inspection program since no bolting two inches and over is used.

B 3.4, 3.5, 3.6 This item has been deleted in the inspection program since no bolting two inches and over is used.

B ;.1 Safe end inspection in branch piping is deleted since branch piping has no safe ends.

B 4.2, 4.3, 4.4 This item has been deleted in the inspection program since no bolting 2 inches and over is used.

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Appendix B ( Continued)

B 5.4 The feasibility of volumetric examination has not yet been determined. The examination will be performed if feasible and according to the schedule designated in the Examination Plan. If extensive grinding is not required to prepare the surface of the pump casing adjacent to the weld for surface examination, surface examination will be performed to supplement the volumetric examination.

B 5.6 There is currently no known technique available to volu-metrically inspect the pump casing welds. Research is underway to overcome this problem. When proven techniques are available, consideration will be given to the inclusion of these welds in the inspection program. An external surface examination of pump surfaces and welds is not con-sidered possible due to the roughness of the castings. An internal surface examination is impractical due to the high exposures that would be involved (the exam would require a minimum of 16 man-hours; the radiation levels can be expected to be about 5R/hr area and 7R/hr contact). The District's position is that a visual examination, performed only if pump is dissembled for maintenance permitting such inspection, is judged to be adequate based upon design, fabrication and accessibility considerations.

B 5.7 The District's position is that a visual examination per-fonned only if pump is dissembled for maintenance, permit-ting such inspection, is judged to be adequate based upon design, fabrication, and accessibility considerations.

B 6.1, 6.2, 6.3 This item has been deleted in the inspection program since no bolting two inches and over is used.

Inaccessible Piping Welds:

Figure No.* Line No. Weld No.

A-22 12 In. - SI-12 16 A-25 12 In. - SI-24 16 A-27 6 In. - SI-14 10 A-27 6 In. - SI-14 11 A-32 3 In. - HPH-22 1 A-32 3 In. - HPH-22 3 A-38 2 In. - HPH-2.12 5 A-42 12 In. - SDC-20 7 The welds listed above are inaccessible for examination because they are located within walls or floors. Areas on either side of the walls or floors containing these piping welds will be examined for signs of leakage during the hydrostatic testing of the piping systems.

• See the 10-Year Inservice Examination Plan, Fort Calhoun Nuclear Station Unit No. 1

APPENDIX IC EXCEPTIONS TO COMPLIANCE WITH TABLE IWC-2600 Inaccessible Piping Welds:

Figure No.* Line No. Weld No.

B-12 12 In LPSI-12 4 B-13 12 In-LPSI-14 7 B-13 12 In-LPSI-14 10 B-13 12 In-LPSI-14 11 B-14 12 In-LPSI-22 10 B-15 12 In-LPSI-24 4 The welds listed above are inaccessible for examination because they are located within walls or floors. ..reas on either side of the walls or floors containing these piping welds will be examined for signs of leakage during the hydrostatic testing of the piping system.

Examination Category C-D; Pressure-Retaining Bolting Exceeding 1 inch in Diameter ,_

An exception to the requirements of the Summer 1975 addenda of the Section XI Code is taken in regard to pressure-retaining bolting exceeding 1 inch in diameter. The District proposes to comply with the Summer 1976 addenda which modifies the bolting examination requirements to examine only the pressure-retaining bolting exceeding 2 inches in diameter. Since the Summer 1976 and all subsequent addenda to the Section XI Code have adopted the 2-inch diameter and greater examination requirement, the potential for failure and the consequences thereof appear to be of little concern, The code requirement of the Summer 1975 addenda is deemed to be impractical in relation to the level of safety achievad by parforming the examination versus the manpower and monetary expenditures involved.

• See the 10-Year Examination Plan, Fort Calhoun Nuclear Station Unit No.1 APPENDIX ID Inaccessible Piping:

Buried raw water lines from the intake structure to the auxiliary building can-not be tested since the isolation valves are not designed to be leak-tight shut-off valves. Flow instrumentation in the system is capable of detecting signficant leaks by sensing a reduction of flow.

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PART 2: Class 1, 2, and 3 Pump and Valve Tests 2.1 Scope and Responsibility 2.1.1 The P and ID's of Appendix 1A identify the Location of each Class 1, 2, and 3 pump and valve.

2.1.2 Class 1, 2, and 3 pumps to be examined under Subsection IWP, the methods of examination for each pump, and exceptions to the tests of Subsection IWP are found in Appendix 2A. The Class 1, 2, and 3 valves to be examined under Subsection IWV, the methods of examination for each valve, and exceptions to the tests of Subsection IWV are found in Appendix 2B.

2.2 Inspection Intervals 2.2.1 The inspection intervals for Class 1, 2 and 3 pumps are in accordance with Article IWP-3000 of Reference (1) with exceptions as found in Appendix 2A. The inspection intervals for Class 1, 2, and 3 valves are in accordance with Article IWV-3000 of Reference (1) with exceptions as found in Appendix 2B.

2.3 Examination Categories 2.3.1 The examination categories for each Class 1, 2, and 3 pump valve have been determined from the appropriate articles of Subsection IWP and IWV of Reference (1), respectively, with exceptions, and are found in Appendix 2A and Appendix 2B, respectively.

2.4 Examination Methods 2.4.1 The methods to be used to examine Class 1, 2, and 3 pumps and valves have been determined from the appropriate articles of Sub-sections IWP and IWV of Reference (1),

respectively. These methods, along with exceptions, are listed in Appendix 2A and Appendix 2B for Class 1, 2, and 3 pumps and valves, respectively.

2.5 Evaluation of Examination Results

2.5.1 Pumps

2.5.1.1 The evaluation of examination results shall be in accor-dance with Subarticle IWP-3200 and Table IWP-3100-2 of Reference (1) as appropriate.

2.5.2 Valves

2.5.1.2 The evaluation of examination results shall be in accordance with the appropriate Subarticles of Article IWV-3000 of Reference (1).

2.6 Records and Reports

2.6.1 Records and reports for the inspection of Class 1, 2, and 3 pumps shall be made in accordance with Article IWP-6000 of Reference (1). Records and reports for the inspection of 1

Class 1, 2, and 3 valves shall be made in accordance with Article IWV-6000 of Reference (1).

2.7 Repair Requirements

2.7.1 Pumps

2.7.1.1 Repairs will be made as required by Reference (1), Sub-4 section IWP.

2.7.2 Valves

2.7.2.1 Repairs will be made as required by Reference (1), Sub-section IWV.

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t' APPENDIX 2A INSERVICE INSPECTION OF PUMPS Discussion: All the pumps that require an inservice tests for operational readiness under the ASME Boller and Pressure Vessel Code,Section XI, Sub-section IWP are listed below. The inservice test parameters with test frequencies are tabulated for each pump. The requested test exceptions and basis for each exception are given for the applicable parameters.

General: All the pumps listed are directly coupled to induction motor drivers; therefore, the rotation speed need not be measured as prescribed in Subarticle 4400. Operating modes, as designated in this appendix, are as follows: Mode 1- Power Operation, Mode 2 - Hot Standby, Mode 3 - Hot Shutdown, Mode 4 - Cold Shutdown, Mode 5 - Refueling Shutdown.

Low Pressure Safety Injection Pumps SI-1A, B Class 2 Function: The LPSI pumps are available for safety injection of borated water into the reactor coolant system following a LOCA and are used to remove residual heat for cold shutdowns.

Containment Spray Pumps SI-3A, B, C Class 2 Function: The CS pumps are available to spray borated water into containment following a LOCA.

High Pressure Safety Injection Pumps SI-2A, B, C Class 2 Function: The HPSI pumps are available for safety injection of borated water into the reactor coolant system following a LOCA and are used to maintain the required water level in the safety injection tanks.

Operating Modes Subarticle Required For Test Parameter Frequency Exceptions Testing Inlet Pressure Quarterly IWP-3100, 3400 1, 2, 3, 4 or 5 Differential Pressure Quarterly IWP-3100, 3400 1, 2, 3, 4 or 5 Vibration Amplitude Quarterly IWP-3400 1, 2, 3, 4 or 5 Lubrication Level Quarterly IWP-3400 1, 2, 3, 4 or 5 Bearing Temperature Yearly - 1, 2, 3, 4 or 5 Exceptions:

IWP-3100 Inlet and differential pressure measurement Basis: Inlet pressure for these tests will be determined by measuring the static head tank level.

I Exceptions IWP-3400 Inlet pressure, differential pressure, vibration amplitude, and lubrication level will be measured on a quarterly schedule in lieu of monthly.

Basis: These pumps operate infrequently, and degradation is more likely to result from usage than from periods of inactivity.

Monthly testing imposes a manpower hardship that is not commensurate with an increase in quality or safety. Testing all eight safety injection and containment spray pumps requires a total of 30 man-hours, and a licensed control room operator must be diverted from his primary responsibility of monitoring plant equipment that is in operation.

Monthly testing subjects the persons conducting the test to adverse working conditions for extended periods of time. Two men are required in the pump rooms for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during the test. The pump rooms typically have a radiation level of 10 m-rem /hr, reniting in a total exposure of 240 m-rem during the performance of each test.

In addition, running the pumps represents a noise hazard and ambient temperatures of around 95*F with a relative humidity of near 100%.

During the test, each pump is unavailable to perform its safeguard function.

The safety injection and containment spray pumps are low-mainten-ance, low-failure rate items. The containment spray pumps SI-3A, B, and C operate essentially only during tests. Maintenance records show these pumps have not required repair in eight years. The high pressure safety injection pumps SI-2A, B, and C are operated only during tests and to fill safety injection tanks during plant opera-tion. Maintenance records show that one seal was replaced in eight years. The low pressure safety injection pumps operate during tests and as shutdown cooling pumps during cold shutdown periods. These pumps operate for considerably longer periods than the other pumps and maintenance records indicate that each pump required seal repair once. Thus, the plant maintenance records support the caclusions that the pumps are reliable and degradation is the result of use.

Monthly testing requires that each pump be run eight (8) hours longer per year than quarterly testing would require.

Little or no additional increases in the level of safety or quality would accompany monthly testing because the pumps are historically reliable; redundant components exist for each pump; the pumps are lined up for their safety function and are essentially inactive during normal operations. Monthly tests further detract from a level of safety by subjecting workers to unnecessary radiation exposure, harsh working conditions, and by increasing the wear on the pumps.

Charging Pumps CH- 1A, B, C Class 2 Function: The charging pumps are provided to return the purification flow to the reactor coolant system during plant steady state operations.

Operating Mode Test Parameter Frequency Required for Testing Inlet Pressure Monthly 1, 2 or 3 Differential Pressure Monthly 1, 2 or 3 Flow Rate Monthly 1, 2 or 3 Vibration Amplitude Monthly 1, 2 or 3 Lubricant Level and Pressure Monthly 1, 2 or 3 Bearing Temperature Yearly 1, 2 or 3 Component Cooling Pumps AC-3A, B, C Class 3 Function: The component cooling pumps supply cooling water to equipment in the containment and auxiliary building.

Operating Modes Subarticle Required for Test Parameter Frequency Exceptions Testing Inlet Pressure - IWP-3110 -

Differential Pressure -

IWP-3110 -

Flow Rate - IWP-3110 -

Vibration Amplitude Monthly 1, 2, 3, 4 or 5 Lubricant Level and - IWP-3110 -

Pressure Bearing Temperature Yearly 1, 2, 3, 4 or 5 Exceptions IWP-3110 Inlet and differential pressure measurement Basis: System design does not include instrumentation for measuring these parameters. Discharge pressure will be measured on a monthly schedule to help determine possible pump degradation.

l Establishment of a reference value for flow rate.

! Basis: There are many components or subsystems on the I

component cooling water system with several possible piping l configurations. Some of the components are critical l

elements to which the flow rate cannot arbitrarily be varied l for the sake of running a pump test. Consequently, establishing a reference flow rate for a pump test on a periodic basis is impractical.

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Lubricant level or pressure observation.

1 Basis: The pump bearings are cartridge type that have been re-packed with the proper amount of grease and under normal conditions require no further attention for the life of the bearings.

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Reference:

Ingersol Rand Instruction Manual.

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Boric Acid Pumps CH-4A, B Class 3 Function: The boric acid pumps supply blended boric acid to the charging pump header and provide makeup to the SIRW and volume control tanks.

Operating Modes Subarticle Required for Test Parameter Frequency Exceptions Testing Enlet Pressure Monthly IWP-3110 1, 2, 3, 4 or 5 Differential Pressure Monthly IWP-3110 1, 2, 3, 4 or 5 Vibration Amplitude Monthly - 1, 2, 3, 4 or 5 Lubricant Level Monthly - 1, 2, 3, 4 or 5 Bearing Temperature Yearly - 1, 2, 3, 4 or 5 Exceptions:

IWP-3110 Inlet and differential pressure measurement. -

Basis: Inlet pressure will be determined by measuring the static head tank level.

Raw Water Pumps AC-10A, B, C, D Class 3 Function: The raw water pumps provide a cooling medium for the component cooling water system.

Operating Modes Subarticle Required for

! Test Parameter Frequency Exceptions Testing Inlet Pressure - IWP-3110 -

Differential Pressure - IWP-3110 -

Flow Rate - IWP-3110 -

Vibration Amplitude Monthly - 1, 2, 3, 4 or 5 Bearing Temperature - IWP-3110 -

Discharge Pressure Monthly IWP-3110 1, 2, 3, 4 or 5 l

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Exceptions:

IWP-3110 Inlet Pressure measurement.

Basis: System design does not permit direct measurement of inlet pressure. Varying river level and unknown accumulations of sand near the pump suction bell makes it impossible to determine the inlet pressure.

Differential pressure measurement.

Basis: Because of the inability to measure inlet pressure, differential pressure measurement is not possible.

Flow rate measurement.

Basis The system design does not provide an accurate indication of flow rate due to fouling by untreated river water.

Bearing temperature measurement.

Basis: All bearings are inaccessible for temperature measurement. All are submerged in river water.

Discharge pressure vs. motor amperage.

Basis: To be performed in lieu of a differential pressure measurement. An acceptable motor amperage value will be determined over a discharge pressure range of 26 through 40 psig.

Exception to IWP-3220 for All Pump Tests:

All test data shall be analyzed within 4 working days after completion of a test.

Basis: An allowance of 4 working days to analyze test data instead of the 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> requirement will allow greater flexibility in cheduling and performing the various tests.

Special allowances for weekends and holidays will not have to be made in scheduling the tests. The safety related consequences of completing analysis within 4 working days rather than 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> is not considered to be great, since pump tests are performed on a quarterly basis.

APPENDIX 2B INSERVICE INSPECTION OF VALVES DISCUSSION: All valves that require an inserve test for operational readiness under the ASME B and PV Code,Section XI, Subsection IWV, are listed below.

All test parameters, frequencies, and test exceptions are tabulated with each valve.

It has been determined that there are no Category D valves at the Fort Calhoun Station, Unit No. I which are subject to the inservice inspection program.

All locked valves are given operational checks to verify position in accordance with Operating Instructions for the affected system, satisfying the requirements of Category E.

~.

TABLC 28-1 The following Category A valves are listed in groups representing those valves which must be tested simultaneously due to system configuration.

1. TCV-202, HCV-204

2. HCV-241. HCV-206

3. HCV-506A, HCV-506B

4. HCV-467C, HCV-467D

5. HCV-507A, HCV-507B

6. HCV-467A, HCV-467B

7. HCV-438C, HCV-4380

8. HCV-438A, HCV-438B

9. HCV-500A, HCV-500B

10. HCV-2983, SI-185, HCV-2956, HCV-2976, HCV-2936, HCV-2916, PCV-2949, HCV-2969, PCV-2909, PCV-2929

11. HCV-509A, HCV-5098

12. HCV-508A, HCV-508B

13. HCV-882, VA-289

14. HCV-425A, HCV-425B

15. HCV-425C, HCV-425D

16. HCV-2603A, HCV-2603B

17. HCV-2604A, HCV-2604B

18. HCV-2504A, HCV-2504B

19. PCV-742E, PCV-742F

20. PCV-742G, PCV-742H

21. HCV-746A, HCV-746B

22. HCV-881, VA-280

23. HCV-1560A, HCV-1560B

24. HCV-1559A, HCV-1559B

25. PCV-742A, PCV-742B

26. PCV-742C, PCV-7420

- _ , ._ __. . ~ , . - _ , _ . _ _ _ . . _ .., . , _ _ , _ . . . _ .

CATEGORY A VALVES Max Max. Permissible Exceptions Valve P and ID Leakage Stroke Test Failure Refer to Type Number Location Size Rate tsccm) Time (sec) Schedule Mode Appendix 2C Number Globe CE-E-23866- C3 3/4" 1580 1000 14 R0 N0, FC Ex HCV-241 210-120-1 of 2 150 psig 60 psig CE-E-23866- 3/4" 1580 1000 21 R0 NO, FC Ex HCV-206 Globe C3 210-120-1 of 2 150 psig 60 psig Globe CE-E-23866- A5 2" 32300 5000 51 R0 N0, FC Ex TCV-202 210-120-1 of 2 2500 psig 60 psig Globe CE-E-23866- A7 2" 32300 5000 16 R0 N0, FC Ex HCV-204 210-120-2 of 2 2500 psig 60 psig Butterfly CE-E-23866 B8 24" 15000 30 Q NC, FAI HCV-383-3 210-130-1 of 2 60 psig Butterfly CE-E-23866- B8 24" 15000 30 Q NC, FAI HCV-383-4 210-130-1 of 2 60 psig Globe CE-E-23866- B1 2" 24150 10000 39 Q N0, FC HCV-2983 210-130-1 of 2 350 psig 60 psig 2" 24150 15000 NA NA NC, LC Ex SI-185 Globe CE-E-23866- B1 Category A/E 210-130-1 of 2 350 psig 60 psig CE-E-23866- 1" 20400 10000 12 R0 NC, FC Ex HCV-2956 Globe A3 210-130-2 of 2 250 psig 60 psig 1" 20400 10000 12 R0 NC, FC Ex HCV-2976 Globe CE-E-23866- C3 210-130-2 of 2 250 psig 60 psig 1" 20400 10000 12 R0 NC, FC Ex HCV-2936 Globe CE-E-23866 E3 210-130-2 of 2 250 psig 60 psig i

I i

! CATEGORY A VALVES Max Max. Permissible Exceptions j Valve P and ID Leakage Stroke Test Failure Refer to

Number Type Number Location Size Rate (sccm) Time (sec) Schedule Mode Appendix 2C

< HCV-2916 Globe CE-E-23866- F3 1" 20400 10000 12 R0 NC, FC Ex 210-130-2 of 2 2500 psig 60 psig PCV-2949 Globe CE-E-23866- A3 1" 64500 10000 14 Q NC, FC 210-130-2 of 2 2500 psig 60 psig i PCV-2969 Globe CE-E-23866- C3 1" 64500 10000 14 Q NC, FC

! 210-130-2 of 2 2500 psig 60 psig I PCV-2909 Globe CE-E-23866- F3 1" 64500 10000 14 Q NC, FC

! 210-130-2 of 2 2500 psig 60 psig PCV-2929 Globe CE-E-23866- D3 1" 64500 10000 14 Q NC, FC 210-130-2 of 2 2500 psig 60 psig i PCV-742A Butterfly GHDR-11405- D4 42" 18000 2 R0 NC, FC Ex M-1 60 psig l PCV-742B Butterfly GHDR-11405- E4 42" 18000 2 R0 NC, FC Ex l M-1 60 psig PCV-742C Butterfly GHDR-11405- D4 42" 18000 2 R0 NC, FC Ex ,

i M-1 60 psig i PCV-742D Butterfly GHDR-11405- E4 42" 18000 2 R0 NC, FC - Ex

M-1 60 psig HCV-746A Gate GHDR-11405- E3 2" 5000 8 Q NC, FC M-1 60 psig

! HCV-746B Gate GHDR-11405- E3 2" 5000 8 Q NC, FC l M-1 60 psig i PCV-742E Saunders GHDR-11405- E3 1" 2000 9 Q N0, FC ,

Diaphram M-1 60 psig i

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CATEGORY A VALVES Max Max. Permissible Exceptions Valve P and ID Leakage Stroke Test Failure Refer to Number Type Number Location Size Rate (sccm) Time (sec) Schedule Mode Appendix 2C Saunders GHDR-11405- E2 1" 2000 9 Q N0, FC PCV-742F Diaphragm M-1 60 psig Saunders GHDR-11405- E2 1" 2000 9 Q N0, FC PCV-742G Diaphragm M-1 60 psig Saunders GHDR-11405- E2 1" 2000 9 Q N0, FC PCV-742H Diaphragm M-1 60 psig Butterfly GHDR-11405- D5 4" 8000 R0 NC, FC Ex HCV-881 M-1 60 psig Butterfly GHDR-11405- DS 4" 8000 NA R0 NC, F0 Ex HCV-882 M-1 60 psig VA-280 Butterfly GHDR-11405-M1 E5 4" 8000 NA R0 NC, FAI, LC Ex Category A/E M-1, VA-289 Butterfly GHDR-11405- E5 4" 8000 NA R0 NC, FAI, LC Ex Category A/E M-1, 2-1/2" 5000 NA NA NC, FC Ex HCV-1559A Saunders GHDR-11405- G3 Diaphragm M-5 60 psig 2-1/2" 5000 NA NA NC, FC Ex HCV-1559B Saunders GHDR-11405- G3 Diaphragm M-5 60 psig Saunders GHDR-11405- G4 2" 5000 NA NA NC, FC Ex HCV-1560A Diaphragm M-5 60 psig 2" 5000 NA NA NC, FC Ex HCV-1560B Saunders GHDR-11405- G4 Diaphragm M-5 60 psig 4" 8000 66 NC, FC HCV-500A Saunders GHDR-11405- F3 Q Diaphragm M-6 60 psig Saunders GHDR-11405- F3 4" 8000 66 Q NC, FC HCV-500B Diaphragm M-6 60 psig 2" 5000 16 Q NC, FC HCV-506A Saunders GHDR-11405- A3 Diaphragm M-7 60 psig CATEGORY A VALVES Max Max. Permissible Exceptions Valve P and ID Leakage Stroke Test Failure Refer to Location Size Rate (sccm) Time (sec) Schedule Mode Appendix 2C Number Type Number 2" 5000 16 Q NO, FC HCV-506B Saunders GHDR-11405- A3 Diaphragm M-7 60 psig 81 3/8" 6450 1000 1.5 Q N0, FC Ex HCV-2504A Gate GHDR-11405-M-12 2500 psig 60 psig 3/8" 6450 1000 1.5 Q N0, FC HCV-2504B Gate GHDR-11405- B1 M-12 2500 psig 60 psig

• 01 4" 8000 NA NA NC, FC Ex HCV-1749 Gate GHDR-11405-M-13 60 psig 3" 10000 21 R0 N0, FC Ex HCV-425A Globe GHDR-11405- E2 M-40 60 psig 3" 10000 21 R0 N0, FC Ex HDV-425B Globe GHDR-11405- E3 M-40 60 psig 3" 10000 21 R0 N0, FC Ex HCV-425C Globe GHDR-11405- G2 M-40 60 psig 3" 10000 21 R0 NO, F0 Ex HCV-4250 Globe GHDR-11405- G3 M-40 60 psig A3 6" 10000 75 R0 N0, F0 Ex HCV-438A Globe GHDR-11405-M-40 60 psig 1

B3 6" 10000 54 R0 NO, FC Ex HCV-438B Globe GHDR-11405-M-40 60 psig 6" 10000 75 R0 NO, F0 Ex 4

HCV-438C Globe GHDR-11405- D3 M-40 60 psig D3 6" 10000 54 R0 N0, FC Ex HCV-438D Globe GHDR-11405-M-40 60 psig F3 5000 9 R0 N0, FC Ex HCV-467A Globe GHDR-11405- 1

. M-40 60 psig F3 5000 9 R0 N0, FC Ex HCV-467B Globe GHDR-11405- 1 M-40 60 psig CATEGORY A VALVES Max. Max. Permissible Exceptions P and ID Leakage Stroke Test Failure Refer to Valve- Schedule Mode Appendix 2C Number Type Number Location Size Rate (sccm) Time (sec) 9 R0 NO, FC Ex HCV-467C Globe GHDR-11405- G3 1 1/2 5000 M-40 60 psig 1

9 R0 N0, FC Ex HCV-467D Globe GHDR-11405- G3 1 1/2 5000 i M-40 60 psig 1" 2000 4.8 Q NO, FC HCV-2603A Gate GHDR-11405- A3 M-42 60 psig 1" 2000 4.8 Q NO, FC Ex HCV-2603B Gate GHDR-11405 A2 M-42 60 psig i

1" 2000 5.7 Q NO, FC HCV-2604A Gate GHDR-11405 C2 M-42 60 psig 1" 2000 5.7 Q NO, FC Ex HCV-2604B Gate GHDR-11405 C2 M-42 60 psig A2 3" 6000 26 Q N0, FC HCV-507A Saunders GHDR-11405 Diaphragm M-98 60 psig l

3" 6000 26 Q NO, FC HCV-507B Saunders GHDR-11405 A2 Diaphragm M-98 60 psig 1000 4.8 N0, FC HCV-508A Saunders GHDR-11405 AS 1/2" Q Diaphragm M-98 60 psig 1000 4.8 N0, FC

HCV-508B Saunders GHDR-11405 A5 1/2" Q

~

Diaphragm M-98 60 psig 1000 4.8 N0, FC HCV-509A Saunders GHDR-11405 A5 1/2" Q Diaphragm M-98 60 psig 1000 4.8 NO, FC HCV-509B Saunders GHDR-11405 AS 1/2" Q Diaphragm M-98 60 psig 2" 5000 15 R0 NO, FC Ex i PCV-1849 Saunders Diaphragm 60 psig CATEGORY B VALVES Max. Permissible Exceptions Valve P and 10 Stroke Test Failure Refer to Number Number Location Time (sec) Scheaule Mode Appendix 2C LCV-101-1 CE-E-23866-210-120 B2 NA R0 NC, FC Ex 1 of 2 LCV-101-2 CE-E-23866-210-120-1 B2 NA R0 N0, FC Ex 1 of 2 LCV-218-1 CE-E-23866-210-120 Il 11 Q NO, F0 ,

1 of 2 LCV-218-2 CE-E-23866-210-120 I4 28 R0 NO, FAI Ex 1 of 2 HCV-238 CE-E-23866-210-120 A7 48 Q NO, F0 1 of 2 HCV-239 CE-E-23866-210-120 A7 51 Q N0, F0 1 of 2 HCV-240 CE-E-23866-210-120 A7 50 R0 NO, F0 Ex 1 of 2 .

ooo ,

HCV-258 CE-E-23866-210-121 E3 46 R0 NC, FAI Ex HCV-265 CE-E-23866-210-121 E2 46 R0 NC, FAI Ex HCV-257 CE-E-23866-210-121 F4 20 Q N0, FC Note: LCV-218-3, PCV-210, deleted in 1980 - 1983 Plan reference telecon/Hickle (OPPD) Wang (NRC)/3-23-79, not safety related 00 Removed from 76-80 Program Plan in 79 per Telecon/Hickle/ Wang 3/23/79, added to find version '80 '83 p.p. due to completion of Long Term Core Cooling modification.

000TCV-211-1,2 removed, not safety related.

7 CATEGORY B VALVES Max. Permissible Exceptions Valve P and ID Stroke Test Failure Refer to Number Number Location Time (sec) Schedule Mode Appendix 2C HCV-264 CE-E-23866-210-121 F2 20 Q N0, FC HCV-268 CE-E-23866-210-121 B6 24 R0 NC, FAI Ex FCV-269 CE-E-23866-210-121 C7 6 Q NC, FC HCV-385 CE-E-23866-210-130 F1 72 Q N0, F0 1 of 2 HCV-386 CE-E-13866-210-130 G1 72 Q N0, F0 1 of 2 HCV-344 CE-E-23866-210-130 B3 140 R0 NC, F0 Ex 1 of 2 HCV-345 CE-E-23866-210-130 B4 140 R0 NC, F0 Ex 1 of 2 LCV-383-1 CE-E-23866-210-130 H3 30 Q NO, F0 1 of 2 LCV-383-2 CE-E-23866-210-130 H2 30 Q N0, F0 1 of 2 HCV-347 CE-E-23866-210-130 BS 200 R0 NC, FAI, LC Ex Category B/E 1 of 2 HCV-317 CE-E-23866-210-130 A6 12* Q NC, FAI 2 of 2 51CV-318 CE-E-23866-210-130-2 A6 12* Q NC, FAI 2 of 2 HCV-320 CE-E-23866-210-130 C6 12* Q NC, FAI 2 of 2 HCV-321 CE-E-23866-210-130 C6 12* Q NC, FAI l

i 0 Changed from 1976-1980 ISI Program Plan j

Reference:

USAR Section 6.2.3.6.

i CATEGORY B VALVES Max. Permissible Exceptions Valve P and ID Stroke Test Failure Refer to Number Number Location Time (sec) Schedule Mode Appendix 2C

HCV-314 CE-E-23866-210-130 E6 12* Q NC, FAI i 2 of 2 i HCV-315 CE-E-23866-210-130 E6 12* Q NC, FAI 2 of 2 1 HCV-311 CE-E-23866-210-130 F6 12* Q NC, FAI

• 2 of 2 HCV-312 CE-E-23866-210-130 F6 12* Q NC, FAI 2 of 2

. HCV-331 CE-E-23866-210-130 B6 12* Q NC, FAI 2 of 2 HCV-333 CE-E-23866-210-130 C6 12* Q NC, FAI

, 2 of 2 HCV-348 CE-E-23866-210-130 H6 200 R0 NC, FAI, LC Ex Category B/E 2 of 2

HCV-329 CE-E-23866-210-130 E6 12* Q NC, FAI i 2 of 2 HCV-327 CE-E-23866-210-130 G6 12* Q NC, FAI 2 of 2

, HCV-474 GHDR-11405-M-10 H3 15 Q NO, F0

AC-186 GHDR-11405-M-11 C2 NA Q N0 i AC-187 GHDR-11405-M-11 C2 NA Q NC j HCV-400A GHDR-11405-M-40 A2 18 CS NO, F0 Ex HCV-400B GHDR-11405-M-40 A3 18 CS N0, F0 Ex HCV-401A GHDR-11405-M-40 B3 18 CS N0, F0 Ex HCV-401B GHDR-11405-M-40 B3 18 CS NO, F0 Ex 4

• Changed from 1976 - 1980 ISI Program Plan

Reference:

USAR Section 6.2.3.6.

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CATEGORY B VALVES Max. Permissible Exceptions P and ID Stroke Test Failure Refer to Valve Schedule Mode Appendix 2C Number Number Location Time (sec)

B2 18 CS N0, F0 Ex hcl!-402A GHDR-11405-M-40 B3 18 CS N0, F0 Ex HCV-402B GHDR-11405-M-40 B2 18 CS N0, F0 Ex HCV-403A GHDR-11405-M-40 '

B3 18 CS N0, F0 Ex HCV-403B GHDR-11405-M-40 C2 18 CS N0, F0 Ex HCV-403C GHDR-11405-M-40 C3 18 CS N0, F0 Ex HCV-403D GHDR-11405-M-40 C2 18 CS N0, F0 Ex HCV-402C GHDR-11405-M-40 A4 18 Q NO, F0 HCV-2850 GHDR-11405-M-100 A4 18 Q N0, F0 HCV-2851 GHDR-11405-M-100 B4 18 Q N0, F0 HCV-2852 GHDR-11405-M-100 D1 18 Q N0, F0 HCV-2853 GHDR-11405-M-100 D1 18 Q NO, F0 HCV-2882A GHDR-11405-M-100 D2 Q NO, F0 HCV-2880A GHDR-11405-M-100 ,

D3 18 Q N0, F0 HCV-2881A GHDR-11405-M-100 D3 18 Q N0, F0 HCV-2883A GHDR-11405-M-100 El 45 Q N0, F0 HCV-2882B GHDR-11405-M-100 E2 45 Q NO, F0 HCV-2880B GHDR-11405-M-100 E3 45 Q NO, F0 HCV-2881B GHDR-11405-M-100 E3 45 Q NO, F0 HCV-28838 GHDR-11405-M-100 CATEGORY B VALVES Max. Permissible Exceptions Stroke Test Failure Refer to Valve P and ID Appendix 2C Number Number Location Time (sec) Schedule Mode C3 18 CS N0, F0 Ex HCV-402D GHDR-11405-M-40 D2 18 CS N0, F0 Ex HCV-401C GHDR-11405-M-40 NO, F0 Ex D3 18 CS HCV-401D GHDR-11405-M-40 D2 18 CS NO, F0 Ex HCV-400C GHDR-11405-M-40 N0, F0 Ex D3 18 CS HCV-400D GHDR-11405-M-40 NC, F0 YCV-1045A GHDR-11405-M-252 B1 25 Q B1 25 Q NC, F0 YCV-10458 GHDR-11405-M-252 B1 4 CS NO, F0 Ex HCV-1041A GHDR-11405-M-252 B2 4 CS N0, F0 Ex HCV-1042A GHDR-11405-M-252 NC, FAI Ex B1 110 CS HCV-1041C GHDR-11405-M-252 B1 110 CS NC, FAI Ex HCV-1042C GilDR-11405-M-252 NC, F0 HCV-1107B GHDR-11405-M-253 B2 90 Q B2 90 Q NC, F0 HCV-1108B GHDR-11405-M-253 l C2 51 CS NO, FC Ex HCV-1387A GHDR-11405-M-253 C2 51 CS NO, FC Ex 2

HCV-1387B GHDR-11405-M-253 A2 39 CS N0, FC Ex HCV-1388A GHDR-11405-M-253 A2 39 CS N0, FC Ex HCV-1388B GHDR-11405-M-253 C3 60 Q NC, FAI HCV-1384* GHDR-11405-M-253 C1 30 CS NO, FAI Ex HCV-1385 GHDR-11405-M-253 B2 30 CS NO, FAI Ex HCV-1386 GHDR-11405-M-253 i CAdded to 1980 - 1983 Plan.

4 i .

CATEGORY B VALVES Max. Permissible Exceptions Valve P and ID Stroke Test Failure Refer to Number Number Location Time (sec) Schedule Mode Appendix 2C HCV-1107A GHDR-11405-M-253 B2 60 Q NC, F0 HCV-1108A GHDR-11405-M-253 B2 60 Q NC, F0 HCV-2506A GHDR-11405-M-12 B2 3 CS N0, FC Ex HCV-2506B GHDR-11405-M-12 B2 3 CS NO, FC Ex

HCV-2507A GHDR-11405-M-12 B3 3 CS NO, FC Ex HCV-2507B GHDR-11405-M-12 B3 3 CS NO, FC Ex

! I i

i i

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CATEGORY C VALVES Exceptions Valve P and ID Normal Test Refer to Number Type Number Location Position Frequency Appendix 2C RC-141 Relief CE-E-23866-210-110 G6 NC R0 RC-142 Relief CE-E-23866-210-110 G5 NC R0 CH-159 Relief CE-E-23866-210-120 H3 NC Table IWV-3510-1 1 of 2 CH-181 Relief CE-E-23866-210-120 E2 NC Table IWV-3510-1 1 of 2 CH-182 Relief CE-E-23866-210-120 E4 NC Table IWV-3510-1 1 of 2 CH-183 Relief CE-E-23866-210-120 E6 NC Table IWV-3510-1 1 of 2 CH-198 Check CE-E-23866-210-120 C7 NC Ex Ex 1 of 2 CH-335 Relief CE-E-23866-210-120 Al NC Table IWV-3510-1 Note: Valves CH-223, CH-208, CH-224, CH-336, deleted from 1980 - 1983 Plan.

CATEGORY C VALVES Exceptions P and ID Normal -Test Refer to Valve Frequency Appendix 2C Number Type Number Location Position CH-338 Relief CE-E-23866-210-121 D7 NC Table IWV-3510 r

CH-151 Check CE-E-23866-210-121 C7 NC Q F7 NC R0 Ex SI-102 Check CE-E-23866-210-130 1 of 2 Ex CE-E-23866-210-130 F6 NC R0 SI-108 Check 1 of 2 Ex CE-E-23866-210-130 F6 NC R0 SI-115 Check 1 of 2 Ex SI-100 Check CE-E-23866-210-130 H7 NC Q/R0 1 of 2 Ex SI-113 Check CE-E-23866-210-130 H6 NC Q/R0 1 of 2 Ex CE-E-23866-210-130 F5 NC R0 SI-121 Check 1 of 2 Ex CE-E-23866-210-130 F4 NC R0 SI-129 Check 1 of 2 Ex CE-E-23866-210-130 F3 NC R0 SI-135 Check 1 of 2 Ex CE-E-23866-210-130 F2 NC R0 SI-143 Check 1 of 2 Ex F2 NC R0 S1-149 Check CE-E-23866-210-130 1 of 2 Ex CE-E-23866-210-130 C8 NC R0 SI-160 Check 1 of 2 Ex C8 NC R0 SI-159 Check CE-E-23866-210-130 1 of 2 Ex CE-E-23866-210-130 H3 NC R0 SI-140 Check 1 of 2

7 CATEGORf C VALVES Exceptions Normal Test Refer to Valve P and ID Appendix 2C Type Humber Location Position Frequency Number Ex Check CE-E-23866-210-130 H2 NC Q/R0

, SI-139 1 of 2 Table IWV-3510-1 Relief CE-E-23866-210-130 D3 NC

, SI-298 1 of 2 Relief CE-E-23866-210-130 D4 NC Table IWV-3510-1 SI-299 1 of 2 Ex Relief D1 NC R0 SI-209 CE-E-23866-210-130 1 of 2 Ex Relief B1 NC R0 SI-213 CE-E-23866-210-130 2 of 2 Ex El NC R0 SI-217 Relief CE-E-23866-210-130 2 of 2 NC R0 SI-221 Relief CE-E-23866-210-130 G1 2 of 2 Ex CE-E-23866-210-130 B4 NC R0 SI-207 Check 2 of 2 Ex CE-E-23866-210-130 D4 NC R0 SI-211 Check 2 of 2 Ex CE-E-23866-210-130 E4 NC R0 SI-215 Check 2 of 2 Ex NC R0 SI-219 Check CE-E-23866-210-130 G4 2 of 2 Ex B6 NC R0 SI-208 Check CE-E-23866-210-130 2 of 2 R0 Ex CE-E-23866-210-130 D6 NC SI-212 Check 2 of 2 Ex Ed NC R0 SI-216 Check CE-E-23866-210-130 2 of 2 R0 Ex CE-E-23866-210-130 G6 NC SI-220 Check 2 cf 2 Ex CE-E-23866-210-130 A6 NC R0 SI-195 Check 2 of 2 Ex CE-E-23866-210-130 C6 NC R0 SI-198 Check 2 of 2 Ex E6 NC R0 SI-201 Check CE-E-23866-210-130 2 of 2 CATEGORY C VALVES Exceptions Valve P and ID Normal Test Refer to Type Number Location Position Frequency Appendix 2C Number CE-E-23866-210-130 F6 NC R0 Ex SI-204 Check 2 of 2 CE-E-23866-210-130 A6 NC R0 Ex SI-196 Check 2 of 2 CE-E-23866-210-130 NC R0 Ex SI-199 Check C6 2 of 2 NC R0 Ex SI-202 Check CE-E-23866-210-130 E6 2 of 2 CE-E-23866-210-130 F6 NC R0 Ex SI-205 Check 2 of 2 CE-E-23866-210-130 85 NC R0 Ex SI-194 Check 2 of 2 NC R0 Ex SI-197 Check CE-E-23866-210-130 C5 2 of 2 CE-E-23866-210-130 E5 NC R0 Ex SI-200 Check 2 of 2 NC R0 Ex SI-203 Check CE-E-23866-210-130 G5 2 of 2 GHDR-11405-M-252 14 NC R0 Ex MS-291 Check CE-E-23866-210-130 13 NC R0 Ex SI-175 Check 2 of 2 CE-E-23866-210-130 13 NC R0 Ex SI-176 Check 2 of 2

'1 Note: Valves AC-341, AC-4A-HX, AC-4B-Hx, AC-8-HX-Reliefs deleted from 1980 - 1983 Plan.

i 1

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CATEGORY C VALVES -

• Exceptions Valve P and ID Normal Test Refer to Number Type Number Location Position Frequency Appendix 2C '

MS-292 Relief GHDR-11405-M-252 A2 NC Table IWV-3510 Ex MS-275 Relief GHDR-11405-M-252 Al NC Table IWV-3510 Ex s

MS-279 Relief GHDR-11405-M-252 A1. NC Table IWV-3510 Ex M3-276 Relief GHDR-11405-M-252 Al NC Table IWV-3510 Ex '

MS-277 Relief GHDR-11405-M-252 Al NC Table IWV-3510 Ex MS-280 Relief GHDR-11405-M-252 Al NC Table IWV-3510 Ex MS-281 Relief GHDR-11405-M-252 Al NC Table IWV-3510 Ex MS-278 Relief GHDR-11405-M-252 Al NC Table IWV-3510 Ex MS-282 Relief GHDR-11405-M-252 Al NC Table IWV-3510 Ex 1

l 1

CATEGORY E VALVES i Valve Number P and ID Number Location Locked Postion Notes HCV-208 CE-E-23866-210-120-1 of 2 A3 Open Also Category A SI-185 CE-E-23866-210-130-1 of 2 B1 Closed Also Category B

, HCV-347 CE-E-23866-210-130-1 of 2 BS Closed HCV-2977 CE-E-23866-210-130-1 of 2 G2 Open HCV-2978 CE-E-23866-210-130-1 of 2 F2 Open liCV-2967 CE-E-23866-210-130-1 of 2 G2 Open llCV-2968 CE-E-23866-210-130-1 of 2 F2 Open HCV-2957 CE-E-23866-210-130-1 of 2 G3 Open llCV-2958 CE-E-23866-210-130-1 of 2 F3 Open HCV-2947 CE-E-23866-210-130-1 of 2 H4 Open llCV-2948 CE-E-23866-210-130-1 of 2 F4 Open IICV-2937 CE-E-23866-210-130-1 of 2 11 5 Open i HCV-2938 CE-E-23866-210-130-1 of 2 FS Open llCV-2927 CE-E-23866-210-130-1 of 2 G6 Open

liCV-2928 CE-E-23866-210-130-1 of 2 F6 Open CE-E-23866-210-130-1 of 2 Open ilCV-2917 G7 HCV-2918 CE-E-23866-210-130-1 of 2 F7 Open HCV-2907 CE-E-23866-210-130-1 of 2 G7 Open "

liCV-2908 CE-E-23866-210-130-1 of 2 F7 Open liCV-348 CE-E-23866-210-130-1 of 2 H6 Closed Also Category B 4 VA-280 GHDR-11405-M-1 E5 Closed Also Category A VA-289 GHDR-11405-M-1 E5 Closed Also Category A Fil-171 GHDR-11405-M-253 C5 Open FW-172 GHDR-11405-M-253 05 Open i FW-348 GHDR-11405-M-254 B5 Open FW-350 GHDR-11405-M-254 B5 Open i FW-339 GHDR-11405-M-254 B6 Open i

4 APPENDIX 2C JUSTIFICATION FOR EXCEPTION TO ASME SECTION XI CODE Category A Valves:

HCV-241 This valve is used for reactor coolant pump control bleed-off isolation. It cannot be stroked when the reattor coolant system is pressurized, because controlled bleed-off flow must be maintained to prevent damage to the reactor coolant pump seals. The valve cannot be partial-stroked because it is either fully open or fully closed.

HCV-206 This valve serves as penetration M-7, isolation. This valve cannot be stroked when the reactor coolant system is pressurized because controlled bleed-off flow must be maintained to prevent damage to the reactor coolant pump seal. The valve cannot be partially-stroked because it is either fully open or fully closed.

TCV-202 This valve is used for RCS loop 2A, letdown isolation and temperature regulation. Stroking of this valve quarterly during operation or at cold shutdowns would result in the termination of the charging and letdown flows. This would also isolate the boronmeter, process radiation monitor, and reactor coolant system purification process and would have the potential of causing a reactivity excursion.

This valve cannot be partial-stroked because it is either fully open or fully closed.

HCV-204 The function of this valve is for containment penetration 6 M-2, isolation and letdown control. The stroking of this l valve quarterly during operatioit or at cold shutdowns l would result in termination of the charging and letdown i flows. This would also isolate the boronmeter, process radiation monitor, and reactor coolant system purifcation

, process. In addition, the potential would exist for a l reactivity excursion. This valve cannot be partial-stroked because it is either fully open or fully closed.

SI-185 This valve is used to isolate the fill line for safety injection tanks. It has been designated as Category A/E.

The valve is locked closed, and therefore is not subject to a stroke test. The valve will be leak-tested in accordance with Category A leak testing requi ements.

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-  !!CV -2916, The function of these valves is to permit filling and drain 2936, ing of safety injection tanks. These valves cannot be 2956, stroked because doing so would cause level fluctuations in 2976 the safety injection tanks. The level of the safety injec- l tion tanks is controlled by Technical Specifications, and i stroking the valves may result in a violation of these Technical Specifications.

PCV-742A These valves are used for containment purge air isolation 742B and are closed during normal operations and cold shutdowns.

742C They are in the position required to fulfill their design 7420 functions and when open could provide a direct path for release of contaminants from containment. Therefore, stroking these valves ay result in a potential release of contaminants. In addition, valves PCV-742A and 742C cannot be tested in the direction of their design function in accordance with IWV-3420 due to system configuration. The intent of subsection IWV of the Section XI code, to verify operational readiness is met since testing in the direction opposite to the design function will result in a greater leakage than would be experienced in a test in the preferred direction.

HCV-881 The function of these valves is to isolate containment 882 hydrogen purge. Stroking at cold shutdown or quarterly intervals is not advisable, since doing so would provide a direct path for release of containments from the containment.

VA-280 The valves serve to isolate containment hydrogen purge and 289 are designated as Category A/E. They meet Category E criteria because they are locked closed. Cycling of these valves would provide a direct path for release of contaminants from the containment during power operation or cold shutdown.

HCV-1559A The valves serve to isolate the containment demineralized 1559B water line at M-80. Cycling these valves would decrease containment integrity. In addition, these valves are not required to be open during power operation.

HCV-1560A These valves function to isolate the fill and makeup 1560B demineralized water lines to the pressurizer quench tank.

Cycling of these valves would decrease containment integrity.

These valves are not required to be open during power operation.

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HCV-2504A This valve serves to isolate the containment reactor coolant system sample link at penetration M-45. This valve cannot be leak-tested in the direction of its design function in accordance with IW-3420 due to system configuration. The intent of subsection IW of the Section XI code, to verify oparational readiness is met since testing in the direction opposite to the design function will result in a greater leakage than would be experienced in a test in the preferred direction.

HCV-1749 This valve serves to isolate containment penetration M-74, compressed air penetration. This valve cannot be leak-tested in the direction of its design function in accordance with IW-340 due to system configuration. The intent of subsection IW of the Section XI code, to verify the operational readiness, is met since testing in the direction opposite to the design function will result in a greater leakage than would be experienced in a test in the preferred direction.

HCV-425A These valves serve to isolate containment penetrations M-30 425B and M-53, component cooling system penetrations. Stroking 425C cannot be performed during cold shutdown or at quarterly 425D intervals because failure of these valves in the closed position would terminate cooling to safety injection tanks leakage coolers which would in turn have potential for resulting in hot fluid streams entering ion exchange resins of chemical volume control system, thereby causing damage. These valves cannot be partial-stroked because they are either fully opened or fully closed.

HCV-438A These valves serve to isolate containment penetrations M-18, 438B and M-19, component cooling system penetrations. Stroke-438C testing cannot be perfonned at quarterly intervals or cold 438D shutdown because one or more reactor coolant pumps are in operation at all times and these pumps require lube oil and seal cooling. Stroking of these valves would terminate lube oil and seal cooling. These valves cannot be partial- stroked because they are either fully opened or fully closed.

HCV-467A These valves serve to isolate containment penetrations M-15, 467B and M-11, component cooling system penetrations. These 467C valves cannot be stroked quarterly because failure of the 467D valve during testing would render the nuclear detector well cooling units inoperable. Should the nuclear detector well cooling units fail, Technical Specification 2.13 could not be met. The valve cannot be partial-stroked because it is either fully opened or fully closed.

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HCV-2603B Containment isolation to penetrations M-42 and M-43, nitro-HCV-2604B gen gas header penetrations. These valves cannot be leak-tested in the direction of their design function in accor-dance with IWV-3420 due to system configuration. The  !

intent of subsection IWV of the Section XI code, to ve ify the operational readiness, is met since testing in the direction opposite to the design function will result in a greater leakage than would be experienced in a test in the preferred direction.

PCV-1849 This valve serves to isolate instrument air pressure (via penetration M-7) to containment systems. Stroke-testing cannot be performed at cold shutdown or quarterly since instrument air must be available at all times during operation and cold shutdown. The valve cannot be partial-stroked because it is either fully open or fully closed.

Category B Valves:

LCV-101-1 These valves serve to maintain pressurizer level control.

101-2 Stroke-testing cannot be performed during cold shutdown or quarterly because doing so would disrupt pressurizer level regulation capabilities. Upsetting pressurizer level regulation could result in RCS overpressurization. These valves cannot be partial-stroked during operation for the same reason.

LCV-218-2 This valve functions to provide volume control tank level control. The valve cannot be stroke-tested in either cold shutdown or quarterly because doing so would terminate charging flow to the reactor coolant system and would have the potential for disrupting pressurizer level regulation.

Pressurizer level regulation disruption can lead to reactor coolant system overpressure transients. Partial stroke- testing cannot be performed because the valve is either fully closed or fully opened.

HCV-240 Cycling this valve during operation would cause excess pressurizer spray, causing a reactivity excursion (see LCV-101-1,2).

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HCV-258 These valves serve to isolate concentration boric acid from 265 the charging pump suction header. These valves cannot be cycled during cold shutdown or quarterly because doing so would cause concentrated boric acid to be injected into the reactor coolant system via charging pump suction header gravity feedline. Boration of the primary system during normal operation would cause reactivity transients and possibly shut down the plant and during cold shutdowns would delay startup. These valves cannot be partial-stroked for the same reason.

HCV-268 This valve serves to permit direct feed of concentrated boric acid solution to the charging pump suction header.

This valve cannot be stroke-tested during cold shutdown or quarterly because doing so would align concentrated boric acid storage to the charging pump suction header through the boric acid pumps. Boration of the primary system during normal operation would cause reactivity transients and possibly shut down the plant and during cold shutdowns would delay startup. The valve cannot be partial-stroked for the same reason.

HCV-344 These valves serve as containment spray isolation. Stroke-345 testing during cold shutdown or quarterly is not advisable since the potential for spraying down the containment is increased. These valves represent the only boundary between the safety injection pump header and containment spray nozzles. The valves cannot be partial-stroked for the same reason.

HCV-347 These valves serve to isolate the shutdown cooling line.

348 They cannot be stroked quarterly because the operation of these valves is inhibited by dual pressure interlocks when the reactor coolant system pressure is greater than 265 psia.

HCV-400A, These /alves serve to isolate component cooling to contain-B, C, and D ment air cooling and filtering units. They cannot be cycled 401A, quarterly because doing so would terminate component cooling B, C, and 0 to air cooling and filtering units in containment.

402A B, C, and D 403A B, C, and D

HCV-1041A These valves serve to isolate the main steam headers. They 1042A cannot be tested quarterly during operation because doing so would isolate steam flow in the steam generators and result in a turbine and reactor trip. The valves cannot be partial-stroked because they are either fully opened or fully closed.

HCV-1041C These valves serve to provide a pathway from the steam gen-1042C erator to a steam dump and by-pass valves in the event that the main steam isolation valves close. These valves are also used to pre-heat the turbine and related steam system during startup. Cycling of these valves on a quarterly basis during operation would cause the main steam isolation valves to close, causing the turbine to trip and resulting in a reactor trip. The valve cannot be partial-stroked for the same reason.

HCV-1387A These valves serve to isolate steam generator blowdown.

1387B They cannot be stroke-tested during operation quarterly 1388A because doing so would terminate steam generator blowdown 1388B and distrupt all volatile chemistry control. They cannot be partial-stroked because they are fully opened or fully closed.

HCV-1385 These valves serve to isolate main feedwater to the steam 1386 generators. Quarterly stroke-testing cannot be performed during operation because doing so would isolate feedwater to steam generators resulting in a reactor trip. These volves cannot be partial-stroked because they are either fully opened or fully closed.

HCV-2605A These valves serve as containment isolation valves to isol-2605B ate steam generator blowdown sampling lines. Stroke-testing 2607A cannot performed quarterly during operation because doing so 2607B would terminate blowdown sample line flow. The steam genera-tor blowdown activity monitor is on the sample line.

Technical Specification 2.9(1)d requires that blowdown activity shall be continuously monitored by the steam generator blowdown sample monitoring system.

Partial-stroking cannot be performed since these valves are either fully opened or fully closed.

Category C Valves:

CH-198 This valve functions to prevent back-flow to the charging pump discharging pump discharge header. The valve is normally open and there is no way that back-seating can be tested on reversal of flow due to system piping arrange-ments. Partial strok-testing cannot be performed for the same reason.

SI-159 According to the USNRC Docket 50-285, Paper No. 7590-1:

160 "The U.S. NRC has granted relief from certain requirements of the ASME Code,Section XI, . . . The relief consists of exemption from performing valve exercising at each cold shutdown for check valves SI-159 and 160. In lieu of this, the licensee has visually inspected SI-159 or 160 . . (in 1980 and 1981)".

This relief expires in September 1983.

SI-139 These valves function to prevent back-flow to the safety 140 injection and refueling water tank. They will be part-stroked exercised every three months and full-stroked exercised at refueling outages. Full-stroke testing cannot be performed during cold shutdown or quarterly during operation because doing so would require safety injection to the containment or reactor coolant system. A safety injection to the reactor coolant system during operation would cause uncontrolled boration and would introduce a thermal shock to the system. The recircu-lation line that are used for testing the LPSI and HPSI pumps for partial-stroking are not large enough to fully open the check valves.

SI-102 These valves function to prevent back-flow to high pressure 108 and low pressure safety injection pumps and containment 111 spray pumps. They cannot be testing during operation 121 quarterly or at cold shutdowns because doing so would 129 disrupt safeguard system alignment, and safety injection 135 into the containment or the reactor system would be required 143 for valve testing. Partial stcoking cannot be performed for 149 the same reasons.

SI-100 These valves serve to prevent back-flow from high pressure 113 pressure headers to main safety injection headers. They cannot be fully tested during operation quarterly or during cold shutdowns since to do so would require a safety injection to the reactor coolant system. Partial-stroking quarterly is possible since these pumps can be placed in a minimum recirculation mode of operation.

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SI-207 These valves function to isolate reactor coolant pump leak-211 age flow from the safety injection tanks. These valves 215 cannot be stroke-tested during cold shuts or quarterly 219 during operation to do so would cause drainage of the safety injection tanks. Technical Specifications require safety injection tank levels to be maintained. The valves cannot be partial-stroked for the same reason.

SI-208 These valves function to prevent back-flow from the reactor 212 coolant system throgh the safety injection system. These 216 valves cannot be tested during cold shutdowns or quarterly 220 during operation because to do so would introduce cold charging water to the reactor coolant system causing thermal shock. The valves cannot be partial-stroked for the same reasons noted above.

SI-194 These valves function to prevent back-flow through the safety 195 injection pump discharge headers. These valves cannot be 196 stroke-tested during cold shutdowns or quarterly during oper-197 ation because to do so using the safety injection system 198 would require introducing cold water into the reactor coolant 199 system causing thermal shock and possibly a reactor excursion.

200 To do so using the chemical volume control system would dis-201 rupt charging and letdown flow to the reactor coolant system 202 causing chemical and volume control to the system to be dis-203 rupted.

204 205 SI-175 These valves serve to prevent back-flow from the contain-176 ment spray headers. These valves cannot be tested to the open position since to do so could cause spray in contain-ment. No stroking the valves poses no safety impact for the following reasons:

1. Adequate heat removal from containment can be achived during a DBA by use of only one containment spray header with three containment spray pumps. Hence, only one of :he check valves is required to open.

2. The containment air filtration and cooling system is fully redundant to the containment spray system.

3. The containment air filtration and cooling system contains redundant components. During a DBA, sufficient iodine removal is achieved with 50% of the system operating and sufficient pressure reduction accomplished with any three air coolers operatings.

I APPENDIX 3

' Abbreviations A addition C change EX exceptions FAI fail as is FC fail closed a

F0 fail open ,

FTB fail to bypass NA not applicable NC normally closed NO normally open R0 refueling outage Q quarterly Definitions and Clarifications Inservice testing at cold shutdown: Valve testing should conmence not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after shutdown and continue until complete or plant is ready to return to power. Completion of all valve testing is not a pre-requisite to return to power. Any testing not completed at one cold shutdown should be performed during subsequent cold shutdown to meet the code required testing frequency.

Exception: A deviation from a requirement of ASME IX and applicable addenda due to the impracticality of the requirement within the meaning of 10 CFR 50.55a.

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REFERENCES (1) American Society of Mechanical Engineers Boiler and Pressure Vessel Code, July 1,1974, Edition of Section XI through the Summer 1975 Addenda.

r (2) American Society of Mechanical Engineers Boiler and Pressure Vessel Code, July 1, 1974, Edition of Section V through the Summer 1975 Addenda.

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TABLE 1.1 COMP 0NENTS, PARTS, AND METHODS OF EXAMINATION Table Item Category Components and Parts Examination No. IWB-2500 to be Examined Method Reactor Vessel Bl.1 B-A Longitudinal and circumferential shell Volumetric welds in core region Bl.2* B-B Longitudinal and circumferential welds Volumetric in shell (other than othse of Category B-A and B-C)

Bl.3 B-C Vessel-to-flange and head-to-flange Volumetric circumferential welds Bl.4 B-D Primary nozzle-to-vessel welds and Volumetric nozzle inside radiused section Bl.5. B-E Vessel penetrations, including control Visual (IWA-5000) rod drive and instrumentation penetrations Bl.6 B-F Nozzle-to-safe end welds Volumetric and Surface Bl.7 B-G-1 Closure studs, in place Volumetric Bl.8 B-G-1 Closure studs and nuts, when removed Volumetric and Surface Bl.9 B-G-1 Ligaments between threaded stud holes Volumetric Bl.10 B-_G-1 Closure washers, bushing Visual Bl.11 B-G-2 Pressure-retaining bolting Visual Bl.13 B-I-1 Closure Head Cladding 1) Visual and Surface or

2) Volumetric Bl.14 B-I-1 Vessel Cladding Visual Bl.15 B-N-1 Vessel Interior Visual Bl.17 B-N-3 Core support structures Visual Bl.18 B-0 Control rod drive housings Volumetric Bl.19 B-P Exempted components Visual (IWA-5000)

Pressurizer 82.1 B-B Longitudinal and circumferential welds Volumetric B2.2 B-D Nozzle-to-vessel welds and nozzle-to- Volumetric vessel radiused section B2.3 B-E Heater penetrations Visual (IWA-5000)

B2.4 B-F Nozzle-to-safe end welds Volumetric and Surface B2.8 B-H Integrally-welded vessel supports Visual B2.9 B-I-2 Vessel cladding Visual B2.10 B-P Exempted components Visual (IWA-5000)

B2.11 B-G-2 Pressure-retaining bolting Visual

• Flow baffles allow internal access to only 25% of the meridional welds.

TABLE 1.1 - (Continued)

COMPONENTS, PARTS, AND METHODS OF EXAMINATION Table Examination Item Category Components and Parts to be Examined Method No. IWB-2500 Heat Exchangers and Steam Generators B-B Longitudinal and circumferential welds Volumetric B3.1 including tube sheet-to-head or shell welds on the primary side B-D Nozzle-to-head welds and nozzle inside Volumetric B3.2 radiused section on the primary side B-F Nozzle-to-safe end welds Volumetric B3.3 and Surface Integrally-welded vessel supports Volumetric B3.7 B-H Vessel cladding Visual B3.8 B-I-2 B-P Exempted components Visual (IWA-5000)

B3.9 Visual B3.10 B-G-2 Pressure-retaining bolting Piping Pressure Boundary 84.5 B-J Circumferential and longitudinal pipe welds Volumetric Branch pipe connection welds exceeding Volumetric B4.6 B-J six in, diameter Branch pipe connectionn welds six in. Surface B4.7 B-J diameter and smaller Socket welds Surface B4.8 B-J Volumetric B4.9 B-K-1 Integrally welded supports Support components Visual B4.10 B-K-2 Visual (IWA-5000)

B4.11 B-P Exempted components Pressure-retaining bolting Visual 84.12 B-G-2 Pump Pressure Boundary Pressure-retaining bolts and studs, Volumetric B5.1 B-G-1 in place Pressure-retaining bolts and studs, Volumetric and B5.2 B-G-1 Surface when removed Pressure-retaining bolting Visual B5.3 B-G-1 Volumetric B5.4 B-K-1 Integrally-welded supports Support components Visual B5.5 B-K-2 Visual B5.6 B-L-1 Pump Casing Welds Pump Casings Visual B5.7 B-L-2 Visual (IWA-5000) 85.8 B-P Exempted components Pressure-retaining bolting Visual 85.9 B-G-2

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TABLE 1.1 - (Continued)

COMPONENTS, PARTS, AND METHODS OF EXAMINATION Table Item Category Components and Parts Examination No. IWB-2500 to be Examined Method Valve Pressure Boundary B6.4 B-K-1 Integrally welded supports Volumetric B6.5 B-K-2 Support components Visual B6.6 B-M-1 Valve Body Welds Volumetric B6.7 B-M-2 Valve bodies Visual B6.8 B-P Exempted components Visual (IWA-5000)

B6.9 B-G-2 Pressure-retaining bolting Visual

TABLE 1.2 COMPONENTS, PARTS, AND METHODS OF EXAMINATION Table Item Category Components and Parts Examination No. IWB-2500 to be Examined Method Pressure Vessels C1.1 C-A Circumferential butt welds Volumetric C1.2 C-B Nozzle-to-vessel welds Volumetric C1.3 C-C Integrally-welded supports Surface C1.4 C-D Pressure-retaining bolting Visual and either surface or volumetric Piping C2.1 C-F,C-G Circumferential butt welds Volumetric C2.2 C-F,C-G Longitudinal weld joints in fittings Volumetric C2.3 C-F,C-G Branch pipe-to-pipe weld joints Volumetric C2.4 C-D Pressure-retaining bolting Visual and either surface or volumetric C2.5 C-E-1 Integrally-welded supports Surface C2.6 C-E-2 Support components Visual Pumps C3.1 C-F,C-G Pump casing welds Volumetric C3.2 C-D Pressure-retaining bolting Visual and either surface or volumetric C3.3 C-E-1 Integrally-welded supports Surface C3.4 C-E-2 Support components Visual Valves C4.1 C-F,C-G Valve body welds Volumetric C4.2 C-D Pressure-retaining bolting Visual and either surface or volumetric C4.3 C-E-1 Integrally-welded supports Surface C4.4 C-E-2 Support components Visual

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