Text

Inservice Insp Program for Unit 2
	ML19224D060
Person / Time
Site:	Zion File:ZionSolutions icon.png
Issue date:	07/10/1979
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML19224D051	List: ML19224D050; ML19224D055; ML19224D060;
References
	PROC-790710-01, NUDOCS 7907100578
	Download: ML19224D060 (3)
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ATTnCHMENT 2 INSERVICE INSPECTION PROGRAM FOR ZION STATION UNIT 2 NRC DOCKET NO. 50-304

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322 328

O ZION UNIT f2 INSERVICE INSPECTION PROGRN4 Pages 1 - 10 Introduction Pages 11 - 23 Class 1 NDE Pages 24 - 33 Class 2 NDE Pages 34 - 39 Class 3 NDE Pages 40 - 45 Pump Testing Valve Testing........................... Pages 46 - 83 0

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ZION UNIT #2 INSERVICE INSPECTI3N PROGRAM Second 40 Month Period of First 10 Year Interval The attached tables provide a listing of the Class 1, 2 and 3 pressure-retaining components (and their supports) which are subject t3 the inspection requirements of Subsections IWB, IWC and IWD of Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition, and Addenda through Summer, 1975, as required by Technical Specification 4.3.4.C.

These tabulations identify the components to be inspected, the compo-nents safety class, the applicable code to whicn the component was built, and the method of examination.

Relief from the inspection re-quirements of each Subsection is requested in cases where these in-()I spection requirements have been determined to be impractical.

Where relief is requested, specific information is provided which identifies the applicable code rer,airement, justification for the relief request, and the inspection method to be used as an alternative.

The following provide further clarification concerning the Class 1, 2

and 3 system inspection programs.

(A)

Articles IWC-3000 and IWD-3000 entitled, " Evaluation of Examination Results" are in the course of preparation by the Code Committee and, as yet, are not available for use.

The rules of IWA-3000 will be utilized with the exception that the evaluation of any indications detected during any in-service examinations will be made using the acceptance r

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standards for materials and welds specified in the code under which the specific component was constructed.

(B)

Articles IWC-4000 and IWD-4000 entitled, " Repair Procedures" state that the rules of IWB-4000 shall apply.

It is con-sidered that the repair procedures outlined in IWB-4000 are in this inappropriate for the Class 2 and 3 components program and the rules of IWA-4000 will be applied.

(C)

Requirements for the visual examination of ClaJs 1 systems and components for evidence of leakage during the performance of a system pressure test following each refueling are identi-fied by IWB-5200.

Exception is taken to the implementation of these requirements on those portions of Class 1 systems which are contained between two check valves or two normally

($)

closed valves, where pressure applied to the reactor coolant system will be retained at the first valve in the line, (refer to Figures 1, 2, 3 and 4).

The portions of systems affected by this limitation are:

(1)

Accumulator di= charge lines between check valves 8948 A, B,

C, D and 8956 A, B,

C and D.

(2)

Low head safety injection lines to cold legs between check valves 9001 A, B,

C, D and 9002 A, B,

C, D and high head safety injection to check valves 9012 A, B,

C and D.

(3)

Boron injection lines to cold legs between check

(])

valved 8900 A, B,

D and MOV 8800 A, B, C and D.

Page 2 of 832 33)

(4) High head safety injection to hot 1 cgs between (hh check valves 8949 C and D and 9004 C and D. (5) RHR return to hot legs between check valves 8949 A and B and high safety injection lines to check valves 8905 A and B. (6) RUR take off line between MOV 8701 and 8702. The four systems identified as i, 11, iv and v are all part of the emergency core cooling systems and the portions in question ecch have a non-return check valve between the prf: ry reactor coolant pressure source and the Class 1 to 2 boundary. Consequently pressure applied from the reactor coolant system is retained by the check valve and the portion in question, between this check valve and the boundary (h) valve, would not be pressurized. There are no provisions for pres-surizing these portions of piping to reactor coolant system pressure (2235 psig). The boron injection system, identified as Item iii, will be leak tested using the charging pumps cach refueling outage. Dae to other constraining operating criteria, this portion of the test will be done at the beginning of each refueling outage rather than at the end. In the RHR suction piping, identified as Item vi, electrical inter-locks prevent either valve 8701 or 8702 from being opened at a pressore in excess of 425 psig. Defeating of this interlock at full reactor coolant system pressure would unduly jeopardize the RHR system which is designed for only 600 psig. O Page 3 of 83

i for (D) Subsections IWB and IWC contain differing requirements the hydrostatic testing of Class 1 ano Class 2 systems und components. The implementation of these requirements is im-practical when the only means of pressurizing the Class 2 system is through the Class 1 system, or when the boundary between the two systems is a check valve arranged for flow from Class 2 to the Class 1 system. Exception is taken to the performance of the hydrostatic test requirements as required by Article IWC-2412 (a) on those portions of the Class 2 systems identified below. Each of the listed portions of Class 2 systems has a design pressure of 2485 psig. The operating pressure of the reactor coolant system is 2235 psig. To meet the requirements of IWC-2412 (a ) each line would have to be tested at a pressure kh of 1.05 x 2485 at 500 F, i.e. 2609 psig. To meet the require-ments of IWB-5221, the lines would require testing at 1.02 x 2235 at 500 F, i.e. 2780 psig. The six portions of systems involved either cannot be isolated from the Class 1 systems or can only be pressurized through the Class I systems. "isual examination for evidence of leakage will be conducted on these portions of the systems at the system nominal operating pressure in accordance with the requirements of IWB-5221 for the adjoining Class 1 system. (1) R.C. pump seal bypass line from the orifice to AO valve 2VC 8142. !o Page 4 of 83

I (2) R.C. pump seal leak off line to manually operated valves 8356 A, B, C and D and 8353 A, B, C and D. O (3) R.C. pump scal injection line from check valve 8375 A, B, C and D to manually operated valve 2VC 0081, 0082, 0083 and 0084. (4) Excess letdown from valve 2VC 8381 to HCV 123. (5) Letdown line from valve LCV 459 to orifice outlet valves 8149 A, B and C. (6) PZR steam space sampling line from valve SS9350A to SS9354A, PZR liquid space sampling line from valve SS9350B to SS9353A and loop sampling lines from valves SS9356A, B, C and D and SS9351A and B to ([) valve SS9356A. The potential for inadvertent overpressurization of the reactor coolant system causes additional concerns on t.e advisability of pressurizing CJass 2 systems to considerably higher pressures than the adjacent Class 1 system and relief is requested from implementing the hydrostatic test require-ments of IWC-2412(a) on the CVCS system where such potential exists. The chemical and volume control charging, seal injec-tion and letdown systems are in continuous operation during normal plant operation and are continuously monitored to ensure continued integrity and performance. O 212 n>h 7^ Page 5 of 83 J

i (E) The examination requirements for Class 3 systems and com-ponents as given in the attached tabulation are in accordance with IWD-2410(c) which specifies that 100 percent of the components be examined as required by IWA-5240 and IWD-2600 cither during normal operation or during system inservice testing. An additional requirement of IWD-2410(b) is for the examination of Class 3 systems and components for evidence of leakage during the performance of a system pressure test in accordance with IWD-5000. The code doca not stipulate that certain amounts of these examination requirements be completei within each 40 month period such that the syst<sm prcssure test requirements may be deferred until the end of the ten year inspection interval. However, it should be noted, that these system pressure tests when required are impractical in those (h) systems, such as component cooling, service water, spent fuel pit cooling, and boric acid transfer and recirculation, which are in continuous operation during all modes of plant operation. The continuous functional operation servea to demonstrate the structural and leak-tight integrity of these systems. Visual examinations of these systems will be per-formed at normal operation pressures to verify leak-tightness. (F) As an alternative for I-3121 of Section XI: " Calibration blocks required for the examination of welds in ferritic vesmals 2h inches thick and over will be fabricated from material of the same specification, product form, and heat treatment as one of the materials being joined as allowed by () article T-434.1 in the Winter 1976 Addenda of Section V of the ASME Boiler and Prennure Vessel Code." 322 335 Page 6 of 8 3

t the Code The reason this alternative is requested is that requires that calibration blocks for the examination of welds {g fah-icated in ferritic vesselo 2% inches thick and greater be from material taken from the component nozzle drop out or material from the component prolongation. As a third alter-native, when it is not possible to fabricate the block from material taken from the component, the ulock may be fabri-cated from a material of a specification included in the I is re-apa.icable examination volumes of the component. quired that the acoustic velocity and attenuation of such a block be demonstrated to fall within the range of straight beam longitudanal wave velocity and attenuation found in the unclad components. For the components in Zion Units 1 and 2, particularly the pressurizer and steam generators, it will be impossible to meet the requirements of alternatives 1 or 2. Materials of the specification are readily available, but because all the it would components involved are clad on the inner surfaces, be impossible to obtain a comparison of sound beam velocities di.d attenuation in the unclad component. (G) "As an alternative to using Article 5 of Section V, Appendix III of Section XI of the 1974 Edition, Winter 1975 Addendum of the ASME Boiler and Pressure Vessel Code will be used as The guidance for ultrasonic examination of piping systems." reason thic alternative is requested is that the Code provides no other guideline for the inservice examination of piping G welds. Pege 7 of 83 )?

t Relief is taken from stamping or otherwise physically mark-(II) ing welds for identification and location as required by ((g Appendix I, I-6200. This marking was not performed at the time of the preservice inspection. As an alternative, a means of establishing a uniform datum point for each weld is maintained by procedurally describing datum or reference points such that subsequent relocation of the examination area c.n be achieved with an accuracy of 0.5 inches. Ex-perience has shown the above alternative to be adequate in describing inspections and results. The need for such marking, the resulting radiation exposure of personnel and the potential for introducing undue stresacs in the compo-nents are not considered necessary in lieu of the alternative. (7. ) Tables are attached to provide a listing of the ASME Code g Class 1, 2 and 3 pumps and valves subject to the testing requirements of Subsections IWP and IWV of the ASME Boiler and Pressure Vessel Code, 1974 Edition, and Addenda through Summer, 1975. (J) The tabulation of pumps identifies the pumps to be tested, pump code classes, parameters to be measured and test intervals. The requirements for pump performance as currently specified in the plant technical specification is that de-veloped head and flow be wi+:hin + 10 percent of a point on the haad curve. Relief is requested from pump performance parameters of head and flow from having to meet the allowable 3 ranges.cf test quantities as defined in Table IWP-3100-2 with the substitution of the tole.'nces as currently defined in the n' ant technical spccifications as allowed by IWP-3210., }}} 3) Page.8 of 8 3

(K) Similarly the tabulation of valves identifies the valves to be tested, alve code classes, Section XI Category as []) defined by IWV-2000, and test frequencies. In both tabu-lations, relief from the tes :ing requirements of Section XT is requested in cases where these requirements have been determined to be impractical. Where relief is requested, specific information is provided which identifies the applicable code requirement,. justification for the relief request, and testing method to be used as an alternative. The pump and valve testing programs have been reviewed to ensure that testing the component at the specified interval ill not place the plant in an unsafe condition. (L) The inservice inspection and testing programs outlined in the attached tabulations have been developed as a result of a design review. Should certain ASME Section XI Code require-ments be discovered to be impractical due to unforeseen rea-sons during the process of performing inspections or tests, relief will be requested from the specific Section XI Coae requirement at that time. (M) Radiation levels in certain areas or of certain components may be found to prohibit the access for operators or inspec-tors to perform the inspections or tests described in this Examinations will not be performed if the examiner program. must receive a whole body dose in ex~ess of 1250 mr in order to complete any one examination. If source strengths can-not be reduced ano access is still restricted by considerations O of compliance with the requirements of Regulatory Guides 8.8 Page 9 of 83 }22 bb

t and 8.10, relief will be requested from the specific (h) Section XI Code requirements and alternative examination or test requiremen'ts be proposed. (N) Relief is taken from identifying Class 2 pressure retaining bolting exceeding 1 inch in diameter as examina-tion category C-D. As an altern: '-ive, Class 2 pressure retaining bolting exceeding 2 inches in diameter will be classified as examination category C-D. It is felt that the examinations required for Class 2 bolting need not exceed that of Class 1 bolting. Additionally, guidance is provided by the 1977 Edition including Addenda through the Summer 1978 where examination category C-D applies to bolting exceeding 2 inches. It is felt that no effect on (}) plant safety will result. (O) Codes referenced as being applicable to construction of components in the attached tables are: III A ASME Boiler and Pressure Vessel Code, Section III, Class A Nuclear Vessels III C ASME Boiler and Pressure Vessel Code, Section III, Class C Nuclear Vessels VIII ASME Boiler and Pressure Vessel Code, Section VIII, Pressure Vessels 31.1 USA Standard USAS B 31.1 Code for Pressure Piping 16.5 USA Sta...ard USAS B 16.5 Steel Pipe Flanges, Planged Valves end Fittings 3u.19 USA Standard USAS B 36.19 Stainless Steel Pipe O Page 10 of 83 r7i

Page 11 of 83 ZION UNIT 2 NUCLEAR PLANT INSERVICE INSPECTION PROGRAM ASME CODE CLASS 1 COMPONENTS TABLE k CODE SECTION X I CODE TABLE INB-2500 APPLICABLE IWa-2600 EXAMINATION SYSTEM OR TO EXAMINATION RELIEF ITEM NO. CATEGORY COMPONENT CONSTRUCTION AREA TO BE EXAMINED REOUIREMENT RE00ESTEC Bl.1 B-A Reactor Ves-III A Intermediat2 to Lower Shell Volumetric No sel Course Circumferential Weld Bl.1 B-A Intermediate Shell Course volumetric No Longitudinal Welds (2) Bl.1 B-a Lower Shell Course Longitudinal Volumetric No Welds (2) Bl.2 B-B Lower Head to Shell Circumferen-Volumetr ic No tial Weld Bl.2 B-B Upper Shell Course Mid-course Volumetric No Circumferential Weld B1.2 B-B Upper to Intermediate Shell Volumetric "o Course Circumferential Weld Bl.2 B-D Lower.,aad Ring to Disc Circum-Volumetric ' Yes-Note ferential Weld 1 B1.2 B-B Closure Head Peel Segment Volumetric No Meridional Welds (4) Bl.2 B-B Closure Head Peel Segment to Volumetric Yes-Note Disc Circumferential Weld 2 ut rs) B1.3 B-C Flange to Vessel Weld Volumetric No ~ rs) 31.3 B-C Closure Head to Plange Weld Volumetric No Bl.4 B-D Outlet Nozzle to Shell WeJds volumetric No

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(4)

Page 12 of 83 ZION UNIT 2 NUCLEAR PLANT INSERVICE INSPECTION PROGRAM ASME CODE CLASS 1 COMPONENTS TABLE CODE SECTION X: TABLE IWB-2500 l APPLICABLE CODE SYSTEM OR TO EXAMINATION RELIEF IWB-2600 EXAMINATION g COMPONENT CONSTRUCTION AREA TO BE EXAMINED REOUIREMENT REOUESTED_ ITEM NO. CA"'EGORY Bl.4 B-D Inlet Nozzle to Shell Welds Volumetric No (4) Bl.5* B-E CRDM, Vent and In-Core Instru-Visual No mentation penetrations and CRDM seal welds Primary Nozzle to Safe-End Volumetric No 31.6 B.-F Welds & Surface Bl.7 B-G-1 Closure Studs (In Place) Not Appli-No-Note 3 cable Bl.8 B-G-1 Closure Studs and Nuts Volumetric Yes-Note and Surface and 21 Bl.9 E-G-1 Vessel Flange Ligaments Volumetric No Bl.10 B-G-1 Closure Washers Visual No 31.11 B-G-2 Conoseal Bolting Visual Yes-Note 2 Dl.12 B-H Integrally Welded Supports Not Appli-No-Note 4 cable Bl.13 B-J-l Closure Head Cladding Visual and Yes-Note : Surface ,a N Bl.14 B-J-l Vessel Cladding Visual Yes-Note N Bl.15 B-N-1 Vessel Interior S'trfaces and Visual No U I-ternals ~'El.16 B-N-2 Interior Attachments and. Core Not Appli-No-Note 5 Support Structures cable I \\

Page 13 of 83 ZION UNIT 2 NUCLEAR PLANT INSERVICE INSPECTION PROGRAM ASME CODE CLASS 1 COMPONENTS SECTIGN X TABLE CODE CODE TABLE IWB-2500 APPLICABLE IWB-2600 EXAMINATION SYSTEM OR TO EXAMINATION RELIEF ITEM NO. CATEGORY COMPONENT CONSTRUCTION AREA TO BE EXAMINED REOUIREMENT REaUESTED Bl.17 B-N-3 Core Support Structures Visual. No Bl.18 B-O Control Rod Drive Housings Volumetric No 31.19 B-P Exempted Components Visual No B2.1 B-B' Pressurizer III A Circumferential Shell Welds Volumetric No (5) B2.1 B-B Longitudinal Shell Welds (4) Volumetric No B2.2 B-D Nozzle to Vessel Welf; (6) Volumetric Yes-Note 6 B2.3 B-E Heater Penetrations Visual No B2.4 B-F Nozzle to Safe-End Welds (6) Surface and No Volumetric B2.5 B-G-1 Pressure Retaining Bolting Not Appli-No-Mote I (In Place) cable ~ B2.6 B-G-1 Pressure Retaining Bolting Not Appli- !!o-Mote ' cable B2.7 E-G-1 Pressure Retaining Bolting Not Appli-No-Mote : cable uN B2.8 B-H Integrally Welded Support Volumetric No N 92.9 B-I-2 ' Vessel Cladding Visual Yes-Note L-j

. B2.10 B-P Exempted Components Visual No 22.11 B-G-2 Manway Bolting Visual No 1

P

Page 34 of 83 ZION UNIT 2 NUCLEAR PLANT INSERVICE INSPECTION PROGd3 ASME CODE CLASS 1 v0MPONF9TS 'l SECTICS XI TABL CODE CCDE TABLE IW3-2500 APPLICABLE EXAMINATION RELIEF 1.~d -- 2 6 0 0 EYAMINATION SYSTEM OR TO ITEM NO. CATEGORY COMPONENT CONSTRUCTION AREA TO BE EXAMINED REOUIREMEh"r REOUESTED B3.1 B-B Steam Gener-III A Channel Head to Tubesheet Weld Volumetric No ators (4) (4) (Primary Sidei b3.2 B-D Nozzle to Vessel Welds Volumetric No-Note 9 B3.3 B-F Nozzle to Safe End Welds (8) Volumetric No & Surface B3.4 B-G-1 Pressure Retaining BGiting Not Appii-No-Note E (In Place) cable B3.5 B-G-1 Pressure Retaining Bolting Not Appli-No-Mote 8 cable D3.6 B-G-1 Pressure Retaining Bolting Not Appli-No-Note 8 cable B3.7 B-H Integrally Welded Supports Not Appli-No-Note 8 cable B3.8 B-I-2 Vessel Cladding Visual fes-Note 1 B3.9 B-P Exempted Components Visual No B3.10 B-G-2 Manway Bolting Visual No B4.1 B-F Piping Pres-B 31.l' Safe End to Pipe Welds Volumetric 'Yes-Note .and Surface 17 sure Boundary Pressure Retaining Bciting Not Appli-No-Mote 8 34.2 B-G-1 (In Place) cable g L-:B4.3 B-G-1 Pressure Retaining Bolting Not Appli-No-Note 8 cable .. = - i ti t l

seh - I Page 15 of 83 ZION UNIT 2 NUCLEAR PLANT INSERVICE INSPECTION PROGRAM ASME CODE CLASS 1 COMPONENTS SECTION XI I COD 2 CODE TABLE TABLE IWB-2500 APPLICABLE EXAMINATION RELIEF IWB-2600 EXAMINATION SYSTEM OR { TO 'OUESTED ITEM NO. CATEGORY COMPONENT CO!!STRUCTION AREA TO BE EXAMINED REOUIREMENT 4 B4.4 B-G-1 Pressure Retaining Bolting Not Appli-No-Note 8 cable Circumferential and Longitu-Volumetric Yes-Notes B4.5 B-J dinal Pipe Welds 10, 11,15 17 B4.6 B-J Branch Pipe Connection Welds Volumetric Yes-Note 7 exceeding 6-inch diameter B4.7 B-J Branch Pipe Connection Welds Surface No 6-inch diameter and smaller Socket Welds Surface No B4.8 B-J 34.9 B-K-1 Integrally Welded Support::, Volumetric Yes-Note 12 B4.10 B-K-2 Support Components Visual No B4.11 B-P Exempted Components , Visual ,No Pressure Retain 3ng Bolting Visual No B4.12 B-G-2 B5.1 B-G-1 Reactor Cool-Pressure Retaining Boltihg.(In Volumetric Yes-Note 13 ant Pump Place) L,aB5.2 0-G-1 Pressure Retai.ning Bolting Volumetric Yes-Note and Surface l' N t N Pressure Retaining 1.lting Visual No B5.3 B-G-1 tx B5.4 B-K-1 Integrally Welded Supports Volume.ric No-Mote Visual No B5.5 B-K-2 Support Components

Page 16 of 83 ZION UNIT 2 NUCLEAR PLANT INSERVICE INSPECTION PROGRAM ASME CODE CLASS 1 COMPONENTS SECTION XI TABLE CODE CODE TABLE IWB-2500 APPLICABLE EXAMINATION RELIEF NB-2600 EXAMINATION SYSTEM OR TO ITEM NO. CATEGORY COMPONENT CONSTRUCTION AREA TO BE EXAMINED REOUIREMENT REOUESTED Volumetric Yes-Note Pump Casing Welds 15 B5.6 B-L-1 Visual No Pump Casings PS.7 B-L-2 Visual No Exempted Components B5.3 B~P Pressure Retaining, Bolting Not Appli-No-Note 3 B5.9 .B-G-2 cable B6.1 B-G-1 Valve Pres-B 16.5 Pressure Retaining Bolting (In Volumetric Yes-Note ' sure Boundary Place) Pressure Retaining Bolting Volumetric &Yes-Note 2 B6.2 B-G-1 Surface Pressure Retaining Bolting Visual No B6.3 B-G-1 Integrilly Welded Supports Not Appli-No-Note E Lu.4 'B-K-1 cable Visual No Support Components 36.5 E-K-2 Valve Body Welds Not Appli-No-Note ' B6.6 E-M-1 cable Valve Bodies Visual No BG.7 B-M-2 Visual No u Exempted Compone:its D6.8 B-P g N Pressure Retaining Bolting Visual No B6.9 B-G-2 L< L

NOTES 1. The examination of this weld as required by IWB-2600 is re-stricted from inaide the vessel by the location of the adja-cent incore instrumantation penetrations. Examination of those areas accessible between the penetrations and conduits sill be performed from the ou: side surface to the extent practical as allowed by radiation levels. a. The radiation levclo reported from other plants are gener-ally in the 500-1000 mr/hr range. In reviewing past surveys at Zion the tadiation levels have been found very low ( -s20 mr/hr). Examination will not be performed if the examiner must re-b. ceive a whole body dose in excess of 1250 mr in order to complete any one examination. Examination will be performed on 5 percent (27 inches) of the c. total length of this weld will be performed at or near the end of the ten year inspection interval, as allowed by the Code, and are not scheduled for performance in this second 40 month period. Radiography will not be utilized as an alternative examina-d. tion methot' as access to both sides of the weld would be required. Surface examinations would require basically the same access as ultranonic examination and consequently, radiation levels permitting, ultrasonic examination would be performed. Page 11 of 83 o 7 f, [ Z Jrv

I 2. Review of the configuration and location of Item Bl.2, " Closure head pcel segment to disc weld," indicates that partial volumetric examinations can be performed. Angle beam ultrasonic examinati. will be performed from the peel side of the weld and on the weld. Angle beam examination cannot be performed from the disc side of the weld. This limitation will be reported in the examination Sata as required by I-5121. A visual examination will be con-ducted da.:ing all hydrotests. 3. The reactor vessel closure studs are removed during each re-fueling and there will be no need for examination in place as required by IUB-2600. 4. The reactor vessel supports are integrally forged with the primary nozzles and there are no welds requiring examination. The examination requirement of IWB-2600 is covered by Item Bl.4. 5. This requirement of IWB-2600 is applicable only to Boiling Water & fpc reactors. 6. The geometric configuration of the weld surface prevends ultrasonic examinations being performed to the extent re-quired by IUB-2600. Examinations will be performed to the extent practical from the nozzle and vessel surfaces adjacent to the weld. For Unit 2 the nozzles are welded to the vessel heads and the configuration is as shown in the attacPad Figure E2.2. With the configuration as shown, angic beam ultrasonic examination can be performed from the vessel head and on top of the weld. .n Page 18 of 83 .}ij;

Examination cannot be performed from the nozzle side of the welds. This limitation will be reported in the examination data as required by I -5121. 7. The configuration of the reactor coolant branch nozzle connection welds, Item B4.6 is as shown in Figure B4.6. Volumetric examination can only be performed on butt weld type branch connections. No meaningful volumetric exam-ination can be performed on fillet wcld type branch connections. Surface examination will be performed on 100 percent of the weld and adjacent base material as an altertaative. 8. There are no items in this category that require examination under the requirements of IWB-2600, 9. The steam generator nozzles are integrally cast with the channel head and there are no welds in this category. 10. The arrangements and details of the piping systems and corponents are such that some examinations as required by IWB-2600 are limited due to geometric configuration of accessibility. Generally, these limitations exist at uipe to fitting welds, where exam-ination can only be fully performed from the pipe side, the fitting geometry limiting or even precluding examination from the opposite side. Welds having such restrictions wil.1 be examined to the extent practical. Surface examination may be utilized to supplement volumetric examinations. Examination of the steam generator primary nozzle safe-end to pipe welds, Ite.1 B4.1, is limited both by the nor' c geometry and surface condition and the limited surface pieparation on the Page 19 of 83 32? 34C

m g pipe side of the weld. The surface on the pipe side of *.he weld, which is a cast elbow, is machined for a distance of Ultrasonic approximately 3 inches from the edge of the weld. examination is limited to this distance from the edge of the weld. Examinations can be performed on the surface of the .id, but are severely limited from the nozzle side by the rough, or cast surface. Surface examinations will be performed on 100 percent of the weld and the base metal on the pipe side, The typical configuration is shown in Figure B4.1. 11. In instances where the location of pipe supports or hangers re-strict the access available for the examination of pipe welds as required by IUB-2600, examinations will be performed to the extent practical unless rcmoval of the support is permissible without unduly atressing the system. 12. The piping system integrally welded supports are attached to the pipe by fillet velds. TPc configurations of such welds is such that examinations cannot be performed to the extent required by IND-2600 and only the base material of the pipe wall can be examined by ultrasonic techniques. Surfaca examination will be the performed on integrally welded attachments to supplement volumetric examination. 13. The reactor coolant pump seal housing bolts are of the socket head type aad the configuration is such that ultrasonic ex-aminations as required by IUP-2600 cannot be performed when the bolting is in place. Examinations will only be performed when the seal housing is disassembled for maintenance to the extent required by IWB-2600. e

i o This examination to the extent reai'iued by INI!-2600 vill only 14. be performed when the pump is disassembled for maintenance purposes or at the end of the 10 year interval when disassembly is undertaken foi the performance of pump casing examinations. Volumetric examinations as required by IWB-2600 will be attempted 15. utilizing radiographic techniques. The success of these examina-tions will be dependent upon the availability of high energy gamma sources and the level. of background radiation. Internal ing in the pump may also provide restriction to the extent of fitt examination that can be performed. Relief is taken from performing volumetric exami*ations on longitu-16. din'al welds in the main reactor coolant loop 31 inch, 90 cibows. These velds (two in each of the four loops) were made by the elec-troslag process and no meaningful results using ultrasonic techniques can be obtained due to the high1_ attenuative characteristics of the austenetic grain structur'd. Radiographic techniques are also. not expected to provide meaningful results due to the high levels of background radiation in the piping. Surface examination will be performed as an alternative examination. The circumferential butt weld attaching the pipe to the 15 degree 17. c1ber in cach reactor coolant cold leg is completely c.iclosed within the biological shield and is not accessible for examination as required by IWB-2600. Examinations will be limited to visual for evidence of Icakage during the system hydrostatic test. 9 7 Page 21 of 83 3296 ) J bi

1 1 10. Two of the reactor coolant pumps have 'ntegrally welded supports. The geometric configuration and nature of the materials of the pump support welds are such t:uu ultrasonic examination cannot be performed as required by IUB-2600. Surface examinations will be performed as an alternative. The other two pumps have no elds inthiscate$ryandtherefore, the examination requirements are not applicable. 19. Relief is taken from performing visual and surface or volumetric examinations on closure head cladding and visual examinations on reactor pressurizer and steam generator vessel cladding. The design of these Nessels accounts for the stress.acads to be ade-qua.tely accomadated by the ferritic base material which is examined volumetrically as required b other examination categories. Addi-tional technical guidance is provided by later editions of Section XI where cladding exami ' ions are no longer required. .? 20. Relief is taken fron perfo. ming volumetric examination of bolt,ing-and studs. Due to t.ie inherent geometry of threaded fasteners ar.d signal interference from the threads, volumetric examinations do not provide meaningful results.

Tface e'.aminations of the threaded areas will provide the retmits necessary to ensure the pressure retaining ability of the components.

21. Itclief is taken from volumetric examination of nuts two inches and greater in accordance with IWB-2600, Item Bl.0. Ultrasonic tests will not provide the needed information on axial running defects which are the only defects that would reduce the components abil.ity to perform its intended function. As an alternative, surface excmiru tionn will be performed. These examinations vill provide adequate margins of cafety. _fi';T. 9'/ of M )).}. } r ,,,_m.

i Relief is tal:en from the visual inservi.cc inspection of reactor 22. vessel head,enetration conoscal bciting. These bolts are The normal replaced cach refueling outage with new parts. material receipt inspections performed in accordance with the program will ensure the integrity of Ceco Quality ssurance these components. k t ~m Page 23 of 83 322 351'

7 7 X 1 l' 1 1 1 1 S e e N FT e t t e OEES e e e e t t t t t o o t IDIE o N N o o o o o 3 TOLU N ? N N N N 8 CCEO s s E RE o o o o o o o o o o e e o f S R o ,,Y N N N N N N N N N N N Y 4 NT e 2 ON c c c e - e c c e c c e IE

i. b l

i i il i i ii il il i i, il e TM r r lb lb lb r r lb 'p a r r lb g AE t t pa pa pa t t pa e t t pa pc a NR e e pc pc pc e e pc c e e pc A m m A P II m m A A A m m A a NU u u u u f u u t AO l l t t t l l t r l l t o ME o o o o o o o o u o o o N V V N ER V V N N N V V N S ) 6 ) s s ( 2 t t 1 D r g r g s ( E o n o n d ) N p i p i 6 l s I d p t d p t ( e d M d l u l d l u l W l A l e S o l e S o s e X d e W B e d W B d t W E l W d W l d l e e l e e e l e e o e l MS E W e e d g e W e d g W h e TAT B g s l n g s l n s s NRN l n s e a n l s o a l e s AGE O l a e W l a l e W l l b e LON T e l V F l e V F e u V PRO h F y x h y h T PP A S o l t S o l t S o R M E o t l e o t l e o t ANO R o t a e t o a e o t EOC A t e r h t e r h t e LI l l g s l CT2 d l z e e l d. l g s l l z e e d l z UC a e z t b e a z t b a e z NES e h o n u h e o n u e h o PS H S N I T S H N I T H S N 2SANL TIC ,N I E O NEE L I UCD B T IO A C NVC ECOU C C C OR DITR I I I IEE OL T I I I ZSM CP S I I I NS P N IP A OC t x egr a E vne ) ) RT e e t e i a ON Hrd et d th E ei La i ac MN n gS erS rx EO wn sHe eE TP oae s ge n SM dhb ennb e t. YO tcu cwau g2 SC ext xohT ee LE( Edc( RH I t N 0O 2IY E5TR L2AO B NG ACIE A A D C D A B C D A A B TWMT C C C C C C C C C C C C IAAXC E i I! li 0. 0O E6N 1 1 2 3 4 1 2 3 4 1 1 2 L2 BaM l l 1 1 l l 1 l l l 1 1 ACE C C C C C C C C C C C C T ::T a N N a T. : 1 e t Li t

Page 25 of 83 ZION UNIT 2 NUCLEAR pia %"I INSERVICE INSPECTION PROGRAM ASME CODE CLASS 2 COMPONENTS TABLE CODE SECTION

TABLE IWC-2520 APPLICABLE CODE IUC12600 EXAMINATION SYSTEM OR TO EXAMINATIO:I RELIEF ITEM NO.

CATEGORY COMPONENT CONSTRUCTION AREA 'IO BE EXAMINED REOUIREMENT REOUESTS C1.3 C-C Integrally Welded Supports Not App.i-No-Note 1 cable Cl.4 C-D Pressure Retaining Dolting Not Appli-No-Note 1 cable besidual IIcat II1C IIcad to Shell Welds Voluinetric No Cl.1 C-A bxchangerr, (2) C1.1 C-A (Tube Side) Shell to Tubesheet Welds Volumetric No C1.2 C-B Nozzle to Vessel Welds Volumetric Yes-Note 2 C1.3 C-C Integrally Welded Suppor ts Surface No C1.4 C-D Tubesheet Flange Lolting Not Appli-No-Note 1 cable Cl.1 C-A Seal Water IIIC Cover Weldment to Shell Weld Volumetric Yes-Notes Return Filter 3 and 3 Cl.1 C-A IIead to Shell Weld Volumetric jYes-Notes p and S Cl.2 C-B Nozzle to Vessel Weld Not Appli-No-Note 1. cable 'A N 1.3 C-C Integrally Wolded Supports surface Yes-Note d N C1.4 C-D Pressure Retaining Bolting Not Appli- !No-Note 1 ,j cabic ~$1.1 C-A Seal Water IIIC Shell to Flange Weld Volumetric Yes-Note : l! cat Exchanger i i

1 I I ~3 S_ X 9 e e e e e t N FT t t t t& o OEES o o o o N IDIE N N N M 3 TOLU 8 CCEO o o o o o o o o o o o o E RE N N N N N N N N N N N N f S R o 6 .NT - e - e - e c c c c c c c - e e 2 ON il il il i i i i i i i i l il IE e TM pa pa pa t t t t t t t 'lb lb lb lb lb r r r r r r r pa pa g AE pc pc pc e e e e e e e pc pc a NR A A A m n m m m m m A A P II u u u u u u u MU t t t l l l l l l l t t AO o o o o o o o o o o o o XE N N N V V V V V V V N N ER e i d l d d l l l l e d e e e W l l h W W e l S s l W e s t n 'l e h o t D r g d o l r t S t r E o n l i e r e o N s p i e t h a e o e p I d p t W i S B h t l p M l u l s s z u A e S o l n r b e e z S Y W B l a e u b l o E d e r w t u z N d l e e h T o S T z e MS E e d g S L s t d TAT B s l n o o o N e l g NRN s e a o t o t t l e n AGE O e W l t t t n W i LON T V F l l l e I t PRO y d l n l e l y l PP A o l t a e o e r t r l o R M E t l e e h i h r u e l B ANO R a e H S t S a O t a EOC A e r h i B a r y LI l g s r r s r m w g a CT2 z e e e e n e b ad dd e w UC z t b p p a w u el eI t n NFS o n u p p r o t te ec n a PS N I T U U T L S SW FM I M 2SANL TIC N I E O NEE L I UCD B T IO A C NVC ECOU C OR DITR I IEE OL T I ZSM CP S I NS F N IA A OC ) r e RT e d n)i ONF e4S MN G( l EO TP msl are SM eoh YO ttS SC Sa( l] N 0O 2IY E 5 1' R L2AO B C D A A A A A B B C D B NG ACIE C C C C C C C C C C C C TWMT A A. C ~ 'l I ll I 0. 0O E6N 2 3 4 1 1 1 1 1 2 2 3 4 L2 B'- M 1 1 l l 1 1 l l 1 l 1 l ACE C C C C C C C C C C C C T: T Ui y :n n ,,i

7 Page 27 of 81 ZION rJNIT 2 NUCLEAR PLANT INSERVICE IN9PECTION PROGRAM ASME CODE CLASS 2 COMPONENTS TABLS CODE SECTION XI TA3L". IWC-2520 APPLICADLE CODI

WC 2600 EXAMINATION SYSTEM OR TO EXAMINATION RELIEF

TEM SO.

CATEGORY COMPONENT CUNSTRUCTION AREA TO BE EXAMINED REOUIREMENT REOUESTS Cl.1 C-A Volum Con-IIIC Upper Head to Shell Weld volumetric No trol Tank l C1.1 C-A Lower Head to Shell Weld Volumetric No C1.2 C-B Nozzle to Vessel Weld Hot Appli-No-Note 1 cable i C2.3 C-C Integrally Welded Supports Surface No Cl.4 C-D Manway Bolting Not Appli-No -Note 1 cable Cl.1 C-A Seal Water IIIC Head to Shell Weld Volumetric Yes-Note ! Injection Filters (2) C1.1 C-A Shell to Tubesheet Weld Volumetric Yes-Note ! C1.2 C-B Nozzle to Vessel Weld Not Appli-NO--Note 1 ca'u t e i Cl.3 [ C-C Integrally Wolded Supports Surface Yes-Note i Cl.4 C-D Pressure Retaining Bolting Not Appli-No-Nete 1 rs) cable N Cl.1 C-A Reactor Cool-IIIC Cover Weldment t'o Shell Weld Volumetric Yes-Notcs ~ to; ant Filter 3 and 8 cm C'Cl.1 C-A Head to Shell Weld Volumetric les-Notes 3 and S i i

3 8 4 1 1 X 1 1 s S e e e e t e t5 t e e N FT OEES t o t o o0 t t IDIE o N o Nd N1 o o 3 TOLU N M n N N 8 CCEO s sa sd E RE o e o e o en o o o o o o o f S R N Y N Y4 N Ya N N N N N N N o 4 NT 2 ON - e - c c c c dc e - e IE il i i i i i ni il il e TM lb lb r r r ar lb lb g AE pa e pa t t t t e pa pa e a NR pc c pc e e e le c l pc pc c l P II A a A m m m am a a A A a a MU f u u u uu f u f u AO t r t l 'l l sl r s t t r s XE o u o o o o i o u i o o u i ER N S N V V V VV S V N N S V n s g s i g s g s t n d s n t n t D r i l s d i r i r E o t e t l t o t a N p l W n e l p l I d p o i W o p o p M l u B t o B u B u S A e S t J e X W g u p g s g s E d n B d i n d t s n d t l e i l P i e n d i e n MS E e d n l e n d e l n d e TAT B s l i a W o i l n e i l n NRN s e a i t a e o W a e o AGE O e W t t l t W p t W p LON T V e n a e e m g e m PRO y R e n p R y o n R y o PP A o l r i i l C i l C R M E t l e e ds P e l s e l ANO R a r f ug r a t, a r a t EOC A e r u m tn h u r r C u r r LI l g s u ii c s g o s g o z e s c gt n s e p p s e p CT2 z t e r nt a e t p m e t p UC NES o n r i oi r r n u u r n u PS N I P C LF B P I S P P I S 2SA NL TIC N I E O NEE L I UCD B T IO A C NVC ECOU OR DITR IEE OL T ZSM CP S NS P N IA A OC if s ap m em se Hu RT yt P ON S l E al MN g ua EO n dv TP i io SM p sm) YO i ee2 SC P RR( 'N 0O 2IY G G G E5TR L2AO C C C B NG B C D D 1 2 1 2 ACI E TWMT C C C F F F C E E F D E E IAA XC C C C C C C C C C E l 0. 0O E6N 2 3 4 3 2 3 4 5 6 1 2 3 4 L2 B - M l 1 l 2 2 2 2 2 2 3 3 3. 3 ACE C C C C C C C C C C C C C TWT 'ilC 'll if I 8hIN .I jiI \\ N vI ,]-

1 Page 29 of 83 g ZION UNIT 2 NUCLEAR PLANT INSERVICE INSPECTION PROGRAM 4 ASME CODE CLASS 2 COMPONENTS. b. I h TABLE CODE SECTION X

TABLE IWC-2520 APPLICABLE-CODE CWC-2 60 0 EXAMINATION SYSTEM OR TO EXAMINATION RELIEF kTEM NO.

CATEGORY COMPONENT CONSTRUCTION AREA TO DE EXAMINED REOUIREMENT REOUESTS i C3.1 C-F Centrifugal Pump Casing Welds Volumetric Yes-Note 4 Charging Pumps (2) C3.2 C-D Pressure Retaining Bolting Not Appli-No-Note 1 cable C3.3 C-E-1 Integrally Welded Supports Surface No C3.4 C-E-2 Support Components Visual Go C3.1 C-F Positive Dis < Pump Casing Welds Not Appli-No-Mote 1 placement cable Charging C3.2 C-D Pump Pressure Rc3 ining Bolting Not Appli-No-Note 1 cable C3.3 C-E-1 Integrally Welded Supports Not Appli-No-Note 1 cable C3.4 C-E-2 Support Components Visual No i C4.1 C-F; C-G Valves Valve Body Welds Not appli-No-Note 1 { cable iba N C4.2 l C-D Pressure Retaining Bolting Visual and No ^J Volumetric {jC4.3 C-E-1 Integrally Welded Supports Not Appli-No-Note 13 g cable C4.4 C-E-2 Support Components Visual No

t NOTES 1. There a$e aither no items in this category or items are ex-cluded from examination requirements of IWC-2600 by appli-cation of critoria giver, in IWC-1220. 2. Access for the ultrasonic examination of the residual heat removal heat exchanger nozzle to vessel weld, Item C1.2, is locally restricted by the adjacent vessel supports and the tubeshect flange. It is estimated that 75 percent of the weld can be examined ultrasonically. Surface examinations will be performed on 100 percent of the weld. 3. The thickness of the materials utilized for the construction of this component (0.165 to 0.185 inches) is such that meaning-ful results could not be expected with ultrasonic examination as required by IWC-2600. Surface and visual examination of these welds will be performed as an alternative method. 4. The arrangement and details of the Class 2 piping system and components were designed and fabric,ted before the examination requirements of Section XI of the Code were formalized and scme examinations as required by IWC-2600 are limited or not practical due to geometric configuration or accessibility. Circumferential butt welds, Item C2.1, in Class 2 systems subject to examination are those that occur at geometric discontinuities such as pipe to vessel welds, pipe to fitting welds or fitting to fitting welds. For pipe to fitting or pipe to vessel nozzle welds, examinations can be performed to the extent required by T-522 of Section V from the weld and pipe surfaces. Examination from the Page 30 of 83 322 }}}-

I fitting side will be dependent upon the geometric configuration. Where elbows or tees are concerned, examination can be performed from the fitting side except where the introdos of the fitting prevents adequate ultrasonic coupling. No examination can be performed from the fitting side uhen it is a valve or a flange. In all cases 100 percent of the weld material can be examir In instances where welds occur at fitting to fitting, accer restrictions as outlined above occur on both sides of the weld. In these instances surface examinations will be performed to supplement the limited ultrasonic examinations. 5. In instances where the location of pipe supports or hangers restrict the access available for thc examination of pipe welds as required by IWC-2600, examinations will be performed to the extent practical unless removal or relocation of the support is permissible without unduly stressing the system. Surface examination will be utilized to supplement volumetric examinations to the extent permitted by access. G. Examination of the charging pump casing weld, Item C3.1, by ultrasonic, radiographic or surface examination r2 quires compleue disassembly of the pump casing and removal of the inboard seal housing and rotor assembly. Ultrasonic examination will be con-ducted whenever a pump is disassembled for maintenance reasons. If no such occasion arises the examination will be performed at or near the end of the 10 year interval. 7. The location of support members may prevent ultrasoaic exam-inations being performed to the extent required by ;WC-2600. Fage 31 of 83 2 36'O

i Examinations will be performed to the extent prt :tical unless support components can be removed to provide additional access. Surface examinations will be performed to supplement the volu-metric examination. 8. Radiation levels within the filter cubicles may prohibit the access for operators to perform volumetric or surface exami-nations as required by IUC-2600. If source strengths cannot be reduced and access is restricted by considerations of compliance with the requirements of Regulatory Guides 8.8 and 8.10 due to high radiation levels, examinations will be limited to the performance of visual examinations for evidence of leakage during system pressure tests. a) With the filters in place the expected levels would be 2-3 R/hr. With the filters removed the levels may be lower depending upon crud build-up, b) The filters would have to be removed to a) low the requi5ed examination to be done. Additionally, some flushing would reduce the radiation level for the ultrasonic cxaminer. c) The removal of filters exposes station operational and maintenance personnel to substantial whole body doses (300-500 mr/ man). Since filter removal for ultrasonic examination only would subject personnel to unnecessary exposure the examinations will be scheduled to coincide with normal f 31ter changes. Page 32 of 83 ~ 322 36!

i d) The filters are changed when needed, based on measured differential pressures. The ext.ccted frequency of filter change is: i) Seal Water Return Filter (once/3-4 yrs) li) Seal Water Injection Filters (once/3-4 yrs) lii) Reactor Coolant Fi ter (once or twice/yr) The required examinations, therefore, will be performed in accordance with the Code frequer,cy. Examination will not be performed if the examiner must receive a whole body dose in excess of 1250 mr in order to complete any one examination. 9. The only supports on the secondary side of the steam generators are mechanically attached. There are no integrally welded supports on the secondary side of the steam generators. 10. The same restrictions to the examination of branch pipe to pipe welds, Item C2.3, may occur in Class 2 systems as discussed in note 7. Volumetric examinations will be performed only on butt weld type branch connections. Surface examination will be per-formed as an alternative where volumetric examination is not meaningful. 11. There are no valves with integrally 'cided supports. 323 00; Page 3 3 of 83

Page 34 of 83

7. ION UNIT 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 3 COMPONENTS Code Appli-Component cable to Method of Section XI Code System Description / Identification Construction Examination Relief Requested Component Pumps OCC-003-0A Visual / Operating tb Cooling OCC-004-0B Pressure CCW Heat Exchangers 0CC-001-#0 VIII Visual / Operating No (Shell Side) 2CC-001-f2 Pressure CCW Surge Tank 2CC-002 VIII Visual / Operating No Pressure RHR Heat Exchanger 2RH-003-2A VIII Visual / Operating No (Shell Side) 2RH-004-2B Pressure CVCS Letdown Heat 2VC-003 VIII Visual / Operating No' Exchanger (Shell Side)

Pressure CVCS Seal Water Heat 2VC-001 VIII Visual / Operating.:o Exchanger (Shell Side) Prossure g N Spent Fuel Pit Heat 2SF-007 VIII V isual/ Operating No 04 Exchanger (Shell Side) Pressure C O CVCS Charging Pump 2VC-006 Visual / Operating No iJ Seal Coolers 2VC-007 Pressure High Head SIS Pump 2SI-003 Visual / Operating No Seal Coolers 2SI-004 Pressure RHR Pump Seal Coolers 2RH-001 Visual / Operating No 2RH-002 Pressure Excess Letdown Heat 2VC-002 VIII Visual / Operating No' Exchanger (Shell Side) Pressure

Page 35 of 83 ZION UNIT 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 3 COMPONENTS Code Appli-Component cable to Method of Section XI Code System Description / Identification Construction Examination Relief Requested Component R.C. Pump Oil Coolers RC-110-?A. Visual / Operating No Coo, ling RC-210-2C Pressure ' (Continued) RC-310-2D RC-410-2B Piping B31.1 Visual / Operating No Pressure Hangers and Supports Visual No O 9 N .A C3 O q.? I

Page 36 of 83 ZION UNIT 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 3 COMPONENTS Code Appli-Component cable to Method of Section XI Code System Description / Identification Construction Examination Relief Recuested Chemical Boric Acid Tanks OVC-022 Visual / Operating No and Volume 2VC-022 Pressure Control Boric Acid Transfer 2VC-023 Visual / Operating No Pumps 2VC-024 Pressure Boric Acid Blender 2VC-013 Visual / Operating No Pressure Boric Acid Filter 2VC-021 I. Visual /Op' crating No Pressure Piping B31.1 Visual / Operating No Pr-ssure Hangers and Supoorts Visual No Spent Fuel Spent Fuel Pit Heat 2SF-007 IIIC Visual / Operating No Pit Coolin y Exchanger (Tube Side) Pressure Spent Fuel Pit Pump 2SF-003 Visual / Operating No Pressure u Piping B31.1 Visual / Operating No N Pressure u Hangers and Supports Visual No o 9 8 9

Page 37 of 83 ZION UNIT 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 3 COMPONENTS Code Appli-Component cable to Method of Section XI Code System Description / Identification Construction Examination Relief Recuested Containment S ray Additive Tank 2SC-004 VIII Visual / Operating No Spray Pressure Piping B36.19 Visual / Operating No Pressure Component Supports Visual No s Auxiliary Piping Visual / Operating No Pressure Steam System Hangers Visual No' Auxiliary Auxiliary Feedwater 2FW-005 Visual / Operating No ?cedwater Pumps (Motor Lriven) 2FW-006 Pressure Auxiliary Feedwater 2FW-004 Visual / Operating No Pump (Turbine Driven) Pressure Piping Visual / Operating No Pressure u N Supports and Hangers Visual No u O O L9 i

Page 38 of 83 ZION UNIT 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 3 COMPONENTS Code Appli-Component cable to Method of Section XI Code System Descriptior/ Identification Construction Examination Relief Requested Service RHR Pump (Motor Driven) 2AV-001 Visual / Operating No Water Room Coolers 2AV-002 Pressure Containment Spray Pump 2AV-008 Visual / Operating No Room Coolers 2AV-009 Pressure Containment Spray Diesel 2CS-015 Visual / Operating No Engine Coolers Pressure Charging Pump Room Coolers 2AV-010 Visual / Operating No 2AV-011 Pressure 2AV-012 SIS Pump Room Coolers 2AV-006 Visual / Operating No 2AV-007 Pressure Auxiliary Feedwater Pump 2A Visual / Operating No Coolers 2B Pressure 2C Hydrogen Recombiner Exhaust Visual / Operating No Jacket Cooler Pressure Penetration Pressurization OPP-002 Visual / Operating No Air Compressor Jacket and 2PP-002 Pressure Afterccolcr agJ rd Control Room HVAC System Visual / Operating No v4 Condensers Pressure O Computer Room HVAC Visual / Operating No CJ Condensers Pressure cx

Page 39 of 83 ZION UNIT 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 3 COMPONENTS Code Appli-Component cable to Method of Section XI Code System Descripticn/ Identification Construction Examination Relief Reauested Service Pumps 2SW-001 Visual / Operating No Water 2SW-002 Pressure-2SW-003 Strainers 2SW-004 Visual / Operating No 2SW-005 Pressure Component Cooling Heat OCC-001 Visual / Operating No Exchanger (Tube Side) 2CC-001 Pressure. Diesel Generator 0A-1 Visual / Operating No Intercooler (Tube Side) OA-2 Pressure ~ 2A-1 2A-2 2B-1 2B-2 Diesel Generator OA Visual / Operating No Jacket Water Cooler 2A Pressure (Tube Side) 2B Diesel Generator Lub. Oil OA Visual / Operating No ~ Cooler (Tube Side) 2A Pressure 2B LA Reactor Containment 2RV-001 Visual / Operating No N ventilation Coolers 2RV-002 Pressure u 2RV-003 a 2RV-004 O - 2RV-005 -J Piping Visual / Operating F) Pressure Hangers and Supports Visual No I

Page 40 of 83 ZION UNIT 2 INSERVICE TEST PROGRAM ASME CODE CLASS 1, 2 AND 3 PUMPS ASME CODE TEST SECT' ION XI CODE PUMP IDENTIFICATION PUMP DESCRIPTION CLASS tlEASURED PARAMETERS INTERVAL RELIEF REOUESTED 2VC-006 Charging (HHSI) 2 1. Speed (if variable) N/A 2VC-007 2. Inlet Pressure (Pi) Monthly No 3. Outlet Pressure (Po) . Monthly No 4. Differential Pressure Monthly No (Pi-Po) 5. Flow Rate Monthly No 6. Vibration Amplitude Note 3 Yes-IWP-4500 7. Bearing Temperature Yearly No 8. Lubricant Level or Monthly No-Note 4 Pressure 2RH-001 Residual Heat Removal 2 1. Speed (if variable) N/A 2RH-LO2 ( RHR) 2. Inlet Pressure (Pi) Monthly No 3. Outlec Pressure (Po) Monthly No 4. Differential Pressure Monthly No- '(Pi-Po) 5. Flow Rate Monthly No 6. Vibration Amplitude Note 3 Yes-IWP-4500 7. Bearing Temperature Yearly No 8. Lubricant Level or Monthly No-Note 4 Pressure OCC-003 Component Cooling 3 1. Speed (if variable) N/A (CCW) OCC-004 2; Inlet Pressure (Pi) Note 1 Yes-IUP-3400(a) OCC-005 2. Outlet Pressure (Po) Note 1 Ye s-IUP-34 0 0 (a) OCC-006 4. Differential Pressure Note 1 Yes-IUP-3 4 00 (a) p; (Pi-Po) .,,a OCC-007 5. Flow Rate Note 1 Yes-IUP-3 4 0 0 (al-6. Vibration Amplitude Note 3 Yes-IWP-4500 .0 7. Bearing Temperature Yearly No 3 3. Lubricant Level or Monthly No-Note 4 C3b Pressure l

Page 41 of 83 ZION UNIT 2 INSERVICE TEST PROGRAM ASME CODE CLASS 1, 2 AND 3 PUMPS ASME CODE TEST SECTION XI CODE PUMP IDENTIFICATION PUMP DESCRIPTION CLASS MEAS'; RED PAFAMETERS INTERVAL RELIEF REOUESTED 2SW-001 Service Water (SW) 3 1. Speed (if variable M/A 2SW-002 2. Inlet Pressure (Pi) Monthly Yes-Iv?-4200 Hote 2 2SU-003 3. Outlet Pressure (Po) Monthly No 4. Differential Pressure Monthly No ~(Pi-Po) 5. Flcw Rate Note 2 Yes-IWP-3100 6. . Vibration Amplitude Note 3 Yes-IWP-4500 7. Bearing Temperature Yearly No 8. Lubricant Level or Monthly No-Note 4 Pressure 2FW-005 Auxiliary Feedwater 3 1. Speed (if variable) N/A 2FW-006 (Motor Driven) 2. Inlet Pressure (Pi) Monthly No

3.. Outlet Pressure (Po)

Monthly No 4. Dif.ferential Pressure Monthly No (Pi-Po) 5. Flow Rate Monthly No 6. Vibration Amplitude Note 3 Yes-IWP-4500 7. Bearing Temperature Yearly No 8. Lubricant Level or Monthly Mo-Note 4 Pressure 2CS-001 Containment Spray 2 1. Speed (if variable) N/A 2CS-002 (CS) 2. Inlet Pressure (Pi) Monthly No tra 2CS-003 3. Outlet Pressure (Po) Monthly No ed 4. Differential Pressure Monthly no t/J (Pi-Po) 5. Flow Rate Monthly no E3 6. Vibration Amplitude Note 3 3-IWP-4500 7. Bearina Temperature Yearly "O 8. Lubricant Level or Mon:hly -Mote 4 Pressure i

Page 42 of 83 ZION UNIT 2 INSERVICE TEST PROGRAM ASME CODE CLASS 1, 2 AND 3 PUMPS ASME CODE TEST SECTION XI CODE PUMP IDENTIFICATION PUMP DESCRIPTION CLASS MEASURED PARAMETERS INTERVAL RELIEF REOUESTED 2SI-003 Safety Injection 2 1. ' Speed (if variable) N/A (SIS) .2SI-004 2. Inlet Pressure (Pi) Monthly No 3. Outlet Pressure (Po) Monthly No 4. Differential Pressure Monthly No (Pi-Po) 5. Flow Rate Monthly No 6. Vibration Amplitude Note 3 Yes-IWP-4500 7. Bearing Temperature Yearly No 8. Lubricant Level or Monthly No-Note 4 Pressure 1. Speed (if variable) 2. Inlet Pressure (Pi) 3. Outlet Pressure (Po) 4. Differential Pressure (Pi-Po) 5.' Flow Rate 6. Vibration Amplitude 7. Bearing Temperature 8. Lubricant Level or Pressure 1. Speed (if variable) 2. Inlet Pressure (Pi) r,, ; 3. Outlet Pressure (Po) re 4. Differential Pressure (y (Pi-Po) c3 5. Flow Rate T%o 6. Vibration Amplitude (b 7. Bearing Temperature 8. Lubricant Level or Pressure f

i NOTES 1. Due to the demands of dependent systems, the individual testing of component cooling pumps as required by IWP-3400(a) would jeopardize safe plant operation. Technical Specification 3.8.6 A & B requires a minimum of 3 component cooling pumps operable with one reactor critical. Of the 5 component cooling pumps, one can be inoperable without any offect on the system. Technical Specification 3.8.6C requires some action if 2 pumps are inoperable only witn two reactors critical One reactor may operate indefinitely in this condition. The design heat load is such that two pumps are required o operate during normal plant operation and three pumps required with one unit at full load and the other shut down (para. 9.3.2 of the FSAR). There is no plant operating conditions when a single pump could be run to determine performance parameters as required by IWP-3400 (a). These pumps are visually checked at least once every 8 hour shift by the equipment attendant as part of a required routine. Instru-mentation is installed which will permit the recording of the inlet pressure at each pump. However, pressure measurement on the pump discharge can only be monitored at the common discharge header. The plant design does not incorporate any flow measure-ment instrumentation. Correct performance of these pumps can only be assessed on their continued ability to perform the function for which they were installed. 323 012 Page 43 of 83

1 2. The service water pumps are vertical desicn with no means of direct inlet pressure measurement as required by IWP-4200. Inlet pressure to these pumps will be established by reference to the.1-"el of lake water above the pump suctic.t. Due to the demands of dependent systems, the individual testing of service water pumps as required by IWP-3400(a) would jeopardize safe plant operation. The plant design does not incorporate any flow measurement instrumentation. Technical Specification 3.8.7. B & C required all three service water pumps to be operable. If one o f the three punps is found inoperable, reactor operation is permissable for the seven succeeding days. In addition the service water systems are crosstied between the two units as described-in the FSAR. Corect per-formance of these pumps can only be assessed on their continued ability to perform the function for which they were installed. 3. The component as designed and installed does not have instrumen-tation for the monitoring of vibration amplitudes of the rotating shaft as required by IWP-4510. Portable vibration sensing equipment is available to monitor vibration parameters. The normal maintenance routine is to monitor vibration velo. city in inches per second. This allows a more accurate determination of abnormal vibration at frequencies other than the shaft rotational "need. The " General Machinery Vibration Severity Chart" published by IRD Mechanalysis, Inc. (see attached) will be used as a guide line. The " alert range will be.314 in/sec<[V<(.628 in/sec. The required action range will be Va2.628 in/sec. The test frequency will be as specified in IWP-3000. Page 44 of 83 0i:

4. This l'>arameter is observed daily as a part of normal plant operating procedures. O Page 45 of 83

ZION UNIT #2 INSERVICE VALVE TEST PROGRAM The following table includes all of the valves required to be exercise and leak tested in accordance with ASME Secticn XIr 1973 edition up to and including Sunmer 1975 Addenda, Subseccions IWV. Relief frem some of the requirement of Section XI are requested as indicated in the Relief Request column with e::planations given in the Remarks. The alterr.ative tests are indicated in the Test columns and also explained in the Remarks. Below listed are the symbols used to indicate valve type, valve actuator type, exercise test frequency, and leakage test frequency. Va lve Type: G - Gate DG - Double Disk Gate Gb - Globe D - Diaphragm R - Angle Relief C - Swing Disk Check B - Butterfly N - Needle Actuator Type: AO - Air MO - Motor HO - Hydraulic M - Manual S - Self-Actuating Exercise Test Frequency: O - Quarterly C - Cold Shutdown C1 - Cold Shutdown with no reactor coolant pumps operating. C2 - Cold Shutdown with the reactor vessel head removed. C3 - Cold Shutdown with feedwater and condensate system not operating. R - Refueling Outage I - Frequency Defined by IWV-3510 323 0i': Page 46 of 83

2 FEE : "ain Steam Zion Unit #2 Page S,Of 83 Rev. O Inservice Test Program ~ ' ' Drawing :s'urber: M-500 Test 2o o to .c c E c o cL -c c c c h o E4 U C ,a

c. C H

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'riteJ: Isolation Valve Zion Unit 02 Pg 53 of 83 Rev. O Inservice Test Program Seal Water A.S.M.E. Code Class 1, 2 and 3 Valves Dra. ting N'r.ber: M-512 i Test Toa o c .c o E C O D. C C c c h 1.e o E4 U o H bo H B O m 43 H oC to U c -e4 g .o p j gg Valve o y g g g g y g Me f' Valve 3 6o Category N Number o o4 A B C D E M N M 4 Request Remarks YES Note 10 IWOO60 NA B-4 X 1/2 C S C IWOO61 NA B-4 X 1/2 C S C YES Note 10 YES Note 10 .TWOO62 NA B-5 X 1/2 C S C IWOO63 N A, B-6 X 1/2 C S C YES Note 10 IW0064 NA B-5 X 1/2 C S C YES Note 10 IWOO65 NA B-5 X 1/2 C S C YES Note 10 IW0066 NA B-6 X 1/2 C S C YES Note 10 IW0067 NA C-3 X 1/2 C S C YES Note 10 YES Note 10 IWOO68 NA C-3 X 1/2 C S C IWOO69 NA C-3 X 1/2 C S C YES Note 10 IWOO70 NA C-4 X 1/2 C S C YES Note 10 YES Note 10 IWOO72 NA C-4 X 1/2 C S C YES Note 10 IWOO80 NA D-3 X 1/2 C S iC YES Note 10 IW0081 NA E-5 X, 1/2 C S C IWOO82 NA D-6 X 1/2 C S C YES Note 10 YES Note 10 IWOO83 NA D-6 X 1/2 C S C IWOO84 NA 0-4 X 1/2 C 5 C YES Note 10 IW0160 NA L-2 X 1 R S C YES Note 10 IW0162 NA C-1 X 3/4 C S C YES Note 10 i IW0090 'NA F -- 3 X 1/2 C S C 1 YES Note 10 IWOO95 NA E-5 X 1/2 C S C YES Note 10 g IW0186 NA E-4 X 3/8 C S C YES Note 10 g J C3 r,T e o e

Page 54 of 83 Zion Unit #2 SY; ten: Containment Spray Rev. O Inservice Test Program A.S.M.E. Code Class 1, 2 and 3 Valves Drawir.g Nu-ber: M-514 Test 2 0 o h b e e a u o e-U o e4 tn o H E4 o tn 43 4 oU tp O Cw 3$ V31V I'2 $ o o Valve g g Category y g g g y g Relief Recuest Remarks U C A B C D L' M E' W

un be r MOV-CS0002 2

B-4 X 10 G MO Q 50 R NO Note 7 MOV-CS0003 2 C-3 X 10 G MO O 50 NO MOV-CS0004 2 D-4 X 10 G MO O 50 R NO Note 7 NO MOV-CS0005 2 D-3 X 10 G MO Q 50 MOV-CS0006 2 F-4 X 10 G MO Q 50 R NO Note 7 MOV-CS0007 2 F-3 X 10 G MO O 50 NO NO MOV-CS0008 3 C-4 X 3 G MO Q 15 MOV-CS0009 3 E-4 X 3 G MO O 15 NO MOV-CS0010 3 F-4 X 3 G MO O 15 NO - CS0002 2 B-8 X 14 G M NO Locked Open NO Note 4 CS0003 2 B-8 X 10 C S Q NO Locked Open CS0004 2 B-8 X 10 G M CS0005 2 B-4 X 10 C S Q NO Note 4 NO Locked Open CS0006 2 D-8 X 14 G M NO Note 4 CS0007 2 D-8 X 10 C S Q NO Locked Open CS0008 2 D-8 X 10 G M NO Note 4 CS0009 2 D-5 X 10 C S Q NO Locked Open CS0010 2 F-8 X 14 G M NO Note 4 CS00ll 2 F-8 X 10 C S Q l-- NO Locked Open t/J CS0012 2 F-8 X 10 G M NO Note 4 DJ CS0013 2 D-4 X 10 C S Q NO Locked Open v4 CS0014 3 A-4 X 3 G M NO , Locked Open JS0015 3 D-5 X 3 Gb M YES Note 8 C7 CS0016 2 C-8 X 3 C S T NO Locked Open 2 C-8 X 3 G M ['~CS0017 NO Note 4 CS0018 2 C-9 X 6 C S Q NO Locked Open CS0019 3 A-4 X 3 G M NO Locked Open CS0020 3 E-5 X 3 Gb M YES Note 8 CS0021 2 E-8 X 3 C S T NO Locked Open 3 G P CS0022 2 E-3 X, i 1 g

E75 Z " Contaircent Soray Zion Unit 42 Page 55 of 83 Rev. O Inservice Test Program ~ ~ ~ Drawir.g Nunber: M-514 Test 2o o R .c o E G U O. -e<~* r:: c c 4 C Ed M bo H 8 O m 4 o G U c -d 41 d O tp $ y U yy Valre o y g e g g g y g eM Valve 3 Co Category n Nu.ber U C" A B C D E M N M Request Remarks CS0023 2 D-4 X 6 C S Q NO Note 4 CS0024 3 A-4 X 3 G M NO Locked Open CS0025 3 F-5 X 3 Gb M UO Locked Open ~ YES Note 8 CS0026 2 F-8 X 3 C S T CS0027 2 F-8 X 3 G M NO Locked Open NO Note 4 CS0028 2 E-9 X 6 C S O NO Locked Closed CS0029 2 C-9 X 1 Gb M CS0030 2 C-9 X 1 Gb M NO Locked Closed CS0031 2 E-9 X 1 Gb M NO Locked Closed CS0032 2 E-9 X 1 Gb M NO Locked Closed CS0033 2 P-9 X 1 Gb M NO Locked Closed CS0034 2 F-9 X 1 Gb M NO Locked Closed R NO Locked Closed, Note 7 CS0037 2 B-4 X X 6 G M R NO Locked Closed, Note 7 CS0038 2 B-4 X X 1 G M R NO Locked Closed, Note 7 CS0039 2 C-4 X X 1/2 GL M CS00a0 2 C-4 X X 6 G M R NO Locked Closed, Note 7 R 14 0 Locked Closed, Note 7 CS0041 2 D-4 X X 1 G M CS0042 2; D-4 X X 1/2 Gb M R NO Locked Closed, Note 7 R NO Locked Closed, Note 7 CS0043 2 E-4 X X 6 G M R NO Locked Closed, Note 7 U CS0044 2 E-4 X X 1 G M NCS0045 2 E-4 X X 1/2 Gb M R NO Locked Closed, Note 7 UCS0049 3 C-5 X 3 Gb M NO Locked Closed X 3 Gb M NO Locked Closed CS0050 3 E-5 {CS0051 3 F-5 X 3 Gb M NO' Locked Closed i i

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Page 58 of 83 E' stem: Reactor Coolant Zion Unit $2 f Rev. O Inservice Test Program A.S.M.E. Code Class 1, 2 and 3 Velves Drawing Number: M-J1.6 l Test nm C 0 m .C 0 Es e u m -r O C C N k C b* DC H 6 o m 9 0 09 (n p ~4 0 C -x -d M Valve C d U Ab d C 3C C c u O X t cU . Category N H v 0 u c ..alve c uo -4 e u x 4 0 Rolle. v Nunber U C" A B C D E W N Request Remarks NO RC8010A 1 A-7 'X 6 R S I RC8010B 1 A-7 h 6 R S I NO NO RC8010C 1 A-8 'X 6 R S I RC8025 I A-1 X 3/8 Gb AO O 60 NO Note 9 NO Note 9 RC8026 I A-2 X 3/8 Gb AO O 60 RC8028 I A-1 X 3 D AO O 60 NO Note 9 RC8029 I A-2 X 3 D AO Q 60 NO Note 9 RC8033 I A-2 X 3/4 D AO O 60 NO va J n ru _1

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Volung Control Zion Unit '2 8" Inservice Test Program E0V-O D r n ri n g N u.".b e r : M-518 Test n L1o o C .C o E C U -r C C C >i k o E4 H bO H B O O U o O C e4 v H 00 tn Valve o c o x5 o 0 3c o c u o x Va nre 'o Category N a a o w c c uo .,4 e a x o a pe12cf ClD Mr.be r o c4 A B E G N O 4 Request Rc arks t l MOV-LCV-VCll2B 2 D-6 X 4 G MO O 10 NO MOV-LCV-VCll2C 2: D-- 6 X 4 G MO O 10 NO MOV-LCV-VCll2D 2 'F-7 X 8 G MG O 10 NO MOV-LCV-VCll2E 2 F-7 X 8 G MO O 10 NO MOV-VC8100 2 C-2 X 4 DG M3 0 10 NO Note 9 l 3 G MO 10 MOV-VC8105 2 A-2 X NO Note 9 MOV-VC8106 2 A-2 X 3 G MO O 10 NO Note 9 MOV-VC8110 2 D-4 X 2 G MO O 10 NO MOV-VC8111 2 D-4 X 2 G MO O 10 NO VC8124 2 F-6 X 3/4 R S I NO VC8471A 2 F-6 X 6 G M NO locked Open VC8471Bl2 G-6 X 6 G M NO Locked Open VC8480A'2 D-1 X 2 Gb M YES Notes 9 & 12 VC8480B 2 E-1 X 2 Gb M YES Notes 9 & 12 VC3481AJ2 F-2 X 4 C S 2/C2 NO Note 13 I VC8481D 2 G-2 4 C S 2/C2 NO Note 13 X'! VC8546 2 F-6 X 8 C S 2/C2 NO Note 14 tra N u ".] 7,) (Q t I

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Page 63 of 83 Systsr: Safety Injection Zion Unit #2 Rev. O Inservice Test Progran A.S.M.E. Code Class 1, 2 and 3 Valves Drawing N=ber: M-521 Test ^m C C C .C U Ei c o O. C C h k c E4 U o rd ts o H Ed o c) o .,4 00 tp U C -4 p j U g g# Valve o g g N M O k Valve 3 Co Catego_ry__ Request Re1 arks Nu_.ber o c4 A B C D E M M M 4 YES Note 17 SI8900A 1 A-1 . X 1 C S C2 YES Note 17 SI8900B 1 B-1 X 1 C S C2 YES Note 17 SI8900C 1 B-1 X 1 C S C2 YES Note 17 SI8900D 1 C-1 X 1 C S C2 NO MOV-SI8800A 2 A-2 X 1 Gb MO Q 10 NO MOV-SI8800B 2 B-2 X lb Gb MO Q 10 NO MOV-SIB 800C 2 B-2 X 1 Gb MO Q 10 NO MOV-SI8800D 2 C-2 X 1 Gb MO O 10 NO MOV-SIS 801A 2 A-3 X 4 G MO Q 10 NO MOV-SI8801B 2 B-3 X 4 G MO O 10 NO MOV-SI8802 2 E-4 X 4 G MO Q 10 NO MOV-SI8803A 2 C-6 X 4 G MO O 10 NO MOV-SI8803B 2 C-6 X 4 G MO Q 10 NO MOV-SI8804B #2 P-7 X 8 G MO O 10 NO MOV-SI8806 l2 E-8 X 8 G MO Q 10 NO MOV-SI8807A 2 E-7 X, 4 G MO O 10 NO Opv-sis 807B '2 D-7 x 4 G MO Q 10 M NO Locked Throttled SI8810A [ A-2 X 1 Gb M MO Locked Throttled y SI8810B 2 B-2 X 1 Gb M NO Locked Throttled u SI8810C 2 B-2 X 1 Gb M --j -- NO Locked Throttled CD SI8810D .2 C-2 X lh Gb M NO LEOV-SI8813 2 B-9 X 2 Gb MO Q 10 ~ NO - NV-SI8814 2 C-9 X 2 Gb MO Q 10 NO SI8852 2 A-4 X 3/4 R S I SI8853 !2 E-5 X 3/4 R S I NO SI8858 2 D-7 X 3/4 R S I NO NO SI8870A 2 A-5 X' 1 Gb AO Q 10 SI8870B 2 A-5 X 1 Gb AO Q 10 NO SI8883

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Page 64 of 83 Syster: Safety Iniection Zion Unit #2 Rev. O Inservice Test Program A.S.M.E. Code Class 1, 2 and 3 Valves Drawing Nunber: M-521 Test ^m 0 0 lL C C C h 54 o Ed U c H bo H 6 o m 4> ~4 00 tn U Cw $N Y31VC h E-e o valve 3 8o Category y g g y Relief g o Number U Cd A B C D E m N m 4 Request Remarks YES Note 16 SI89053 1 D-3 X 4 C S C2 NO Note 4 SI8919A 2 E-5 X 3/4 C S O NO Note 4 SI8919B 2 F-5 X 3/4 C S O NO Locked Open SI8920A 2 E-5 X 3/4 Gb M NO Locked Open SI8920B 2 F-5 X 3/4 Gb M NO Locked Open SIB 921A 2 E-5 X 4 G M NO Locked Open SI8921B 2 F-5 X 4 G M YES Note 16 SI8922A 2 E-5 X 4 C S C2 YES Note 16 SI8922B 2 F-5 X 4 C S C2 NO MOV-SI8923A 2 E-1 X 6 G MO Q 10 NO MOV-SI8923B 2 E-7 X 6 G MO Q 10 NO Locked Closed SI8925 2 B-6 X 1 Gb M NO Note 18 SI6926 2 E-7 X 8 C S O/C; YES Note 16 SI8949C 1 F-2 X 8 C S C2 YES Note 16 SI8949D 1 F-2 X 8 C S C2 YES Note 16 SI9004C 1 F-3 X 2 C S C2 YES Note 16 SI9004D 1 F-3 X 2 C S C2 NO MOV-SI9010A 2 E-4 X 4 G MO O 10 NO MOV-SI9010B 2 E-4 X 4 G MO Q 10 MOV-SI90llA 2 E-4 X 4 G MO O f 10 NO l MOV-SI90llB 2 P-4 X 4 G MO O ' 10 NO SI9012A 1 F-1 X 2 C S C2 YES Note 16 YES Note 16 SI9012B 1 F-1 X 2 C S C2 t,a YES Note 16 N) SI9012C 1 E-1 X 2 C S C2' -- YES Note 16 u SI9012D 1 E-1 X 2 C S C2 NO Locked, Throttled SI9013A 2 F-2 X 2 Gb M NO Locked Throttled C3 SI9013B 2 F-2 X 2 Gb M NO Locked Throttled L-1 SI9013C 2 E-2 X 2 Gb M NO Locked Throttled N SI9013D 2 E-2 X 2 Gb M I (

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NOTES 1) Closure of the mainsteam isolation valves during unit oper-ation would result in reactor trip and safety injection actua-tion. To avoid this transient, these valves will be partial-ly strohed every three months. Full stroke testing will be done during cold shutdown. 2) Full stroke exercising of this check valve will be demon-strated by establishing steam flow to the auxiliary feedwater pump turbine. Acceptable pump operation will demonstrate acceptable check valve opening. 3) Closure of the main feecwater isolation valves during unit operation would result in a reactor trip. These valves provide water as the norn al heat removal for the steam gen-erators. To avoid any trcnsient, these valves will not be stroke tested during unit operation or hot shutdown conditions. These valves can only be tested at cold shutdown whenever the feedwater and condensate systems are not in operation. In cold shutdown the steam generators are placed in the " wet lay-up" conditions with the secondary side essentially filled with feedwater. Stroke testing in this condition with the feedwater or condensate systems in operation would introduce an overfill of the steam generators filling the main steam piping. The potential of overpressurizing the secondary side of the steam generators would then exist. This testing period will be each refueling outage as a maximum. 4) Acceptable full stroke exercising of this check valve will be demonstrated by establishing proper pump discharge flow during periodic pump testing. 5) These check valves are passively open during normal operation and their required position to perform their safety function is to be open. The service water and component cooling system are continuously operated and monitored regarding their ability to provide adequate cooling. Upon system start up after a system shutdown the check valve is verified as opening by veri-fication of proper system operation. 6) Same as Note 5. Additionally, the periodic test of the diesel generators demonstrates proper flow through these check valves by verification of proper engine fluids temperatures. 7) These valves will be leak tested in accordance with 10CFR50, Appendix J. 2 hhb Page 78 of 8 3

i 8) Check valves in the spray additive system cannot be exercised without' introducing NaOH contaminants into the spray system. fre-Operability of these three valves will be verified at a quency of one valve cach year. Operability will be verified for free movement by either disassembly of the valve to check the moving parts or by a special full flow flushing procedure. of 9) These valves function as containment isolation valves. No valve seat leakage is specified as they are supplied with a water seal from the Isolation Valve Seal Water (IVSW) systems. The operability of the IVSW system is functionally tested as part of this program. These isolation valves are therefore listed as Category B valves. 10) These IVSW check valves can only be tested by observing flow through downstream tell-tale drain or by disassembly of the This testing valve to verify proper disk freedom of movement. would render the system unable to perform its safety function. These valves will be tested during cold shutdown. 11) Manually operated valves in the reactor coolant pump seal injec-tion lines remain in a normally open condition during unit oper-ation. Manually operated needle valves are adjusted to regulate seal injection flow to maintain correct pressure differentials at the pump seals. The seal injection system remains in opera-tion following any postulated accident contributing to the safety injection flow to the reactor coolant system while main-taining and protecting the pump seals. Should it be required during a protracted accident these valves may b 2 closed and provided with isolation valve seal water. These valves will be manually stroke tested each cold shutdown providing all reactor ecolant pumps are not in operation. This testing period will be each refueling outage as a maximum. Relief is taken from measuring stroke time on manual valves. 12) These manual valves are maintained passively closed during unit operation and are not required to function, other than provide containment isolation, to safely shutdown the reactor or mitigate the consequences of an accident. Exception is taken to the performance of exercising tests as required by INV-3410. 323 04-Page 79 of 83

i 13) Full stroke exercising of the charging pump discharge check valves cannot be demonstrated during unit operation as the reactor coolant system pressure prevents the pumps from reach-ing full injection flow conditions. Partial stroke exercising of these check valves will be demonstrated by establishing proper pump discharge flow during periodic pump testing. Full stroke exercising of this check valve wil.1 be demonstra-tec during cold shutdown providing the reactor vessel head is removed. Performance of this test with the reacter coolant system intact could lead to an inadvertant overpressurization of the system. The alternative method of protecting against overpressurization by partial draining of the reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core. 14) Full stroke exercising of the charging pump suction check valve cannot be demonstrated during unit operation as the reactor coolant system pressure prevents the pumps from reach-ing full injection flow conditions. Partial stroke exercising of this check valve will be demonstrated by verifying charg-ing flow is maintained when the charging pump suction path is transferred from the Volume Control Tank to the Refueling Water Storage Tank during the quarterly valve exercise test. Full stroke exercising of this check valve will be demonstrated during cold shutdown providing the reactor vessel head is removed. Performance of this test with the reactor coolant system intact could lead to an inadvertant overpressurization of the system. The alternative method of protecting against overpressurization by partial draining of the reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core. 15) These check valves cannot be full stroke tested during unit operation as the shut off head of the pumps are lower than reactor coolant system pressure. Partial stroke exercising of these check valves will be demon-strated by establishing proper pump discharge flow during periodic pump testing. Full stroke exercising of this check valve can only be demon-strated during cold shutdown providing the reactor vessel head is removed. This condition is required to establish suction from the RWST and provide system flow conditions similar to design injection flow. Performance of this testing with the reactor coolant system depressurized but intact would not provide adequate serge volume for influx from the RWST to allow the RUR injection system to reach these design flows. The alter-native method of providing a surge volume by partial draining of the reactor coolant system is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core. Page 80 of 83 323 0/10

a 16) These check valves cannot be tested during unit operation as the shutof f hed of the pumps are lower than reactor coolant system pressure. Full stroke testing of all the branch run check valves will be demonstrated by total pump diccharge flow during cold shutdown providing the reactor vessel head is re-moved. Performance of this test with the coactor coolant system depressurized but intact could lead to an inadvertant overpres-surization or the system. The alternative method of protecting against overpressurization by partial draining of the reactor coolant syst'em to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water icvel above the reactor core. 17) These check val.es cannot be tested during unit operation as the injection of co)d, highly borated water would result in a change in reactor core reactivity and undue thermal cycling of the injection nozz1t: 3. Full stroke exercising of all the branch run check valves will be demonstrated by, total pump discharge flow during cold shu':dewn providing the r,! actor vessel head is removed. Performance of this test with :he reactor coolant system intact could lead to an inadvertant :verpressurization of the system. The alternative method of protcoting against overpressurization by partial draining of the, reactor coolant system to provide a surge volume is not considerid a safe practice due to concerns of maintaining adequatewaterhevelabovethereactorcore. 18) These check va:hes cannot be full stroke tested during unit operation as tlp shut off head of the pumps are lower than reactor coolan';. system pressure. Partial strokc; exercising of these check valves will be demon- ' strated by es.ublishing proper pump discharge flow during ' periodic pump testing.) Full stroke ercising of this check valve will be demonstrated during cold lautdown providing the reactor vessel head is removed. Performance hf this test with the reactor coolant system intact could lead ]) an inadvertant overpressurization of the system. The alterntfive method of protecting against overpressurization by partial praining of.the reactor coolant system to provide a surge volvie is not considered a safe practice due to concerns of maintainiir adequate water level above the reactor core. ) 19) These che/x valves cannot be tested during unit operation as the shutoff %ad of the pumps are lower than reactor coolant system pre s su re,' (Con't) I i s / 2 7 (1 1 fi J J t) 4 i / Page 81 of 83 /

Full stroke exercising of all the branch run check valves can only be demonstrated by total pump discharge during cold shut - This condi-down providing the reactor vessel head is removed. tion is required to establish suction from the RNST and provide system flow conditions similar to design injection flow. Per-formance of this testing with the reactor coolant nystem deprea-surized but intact would not provide adequate surge volume for influx from Ehe RWST to allow the RllR injection system to reach these design flows. The alternative method of providing a surge volume by partial draining of the reactor coolant system is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core. 20) The accumuJator check valves cannot be tested during unit operation due to the pressure differential between the accumu-latcrs ( 600 psig) and the reactor coolant system (2235 psig). These valves cannot be full stroke tested except by a rapid depressurization of the reactor coolant system as would occur These during the design basis ccid leg double guillotine break. valves will be partiar stroke tested during cold,. shutdown. is 21) Component cooling water flow to the reactor coolant pumps required at all times the pumps are in operation. Failure of one of these valves in a closed position during exercise test would result in a loss of the cooling flow to the pumps. Exemp-tion is taken to the quarterly exercise test. The valves will be exercise tested during cold shutdown providing all reactor coolant pumps are not in operation. This testing period uill be each refueling outage as a maxinum. .? 22) This check valve is in the containment air particulate and, gas monitor return line. The containment monitor is in continuous operation during unit operation and is also required for con-tainment sampling in the event of an accident since it is passively open and requircd to stay open. The continued proper operation of the system serves to demonstrate proper check valve operation. 23) This manual valve is in the containment air particulate and gas monitor return line. Quarterly closing of this valve during operation would render the system unable to perform its sampling function. Full stroke testing will be performed during cold shutdown. Relief is taken from measuring stroke time on manual valves. R" 3 )n7L.) U JV Page 02 of 83

i 24) The requirement for the containment air particulate and gas monitor return line isolation is one valve. The leak test can only be performed using both the eneck valve (PR0029) and the relief valve in series as one cor.tainment isolation boundary. 25) Closure of these valves during normal unit operation would result in a loss of letdown flow resulting in a reactor in a reactor coolant inventory transient and a subsequent reactor trip. These valves will be full stroke exercised during cold shutdown as required by ASME Section XI, IWV-3410 (b) (1). 26) These valves are located in a closed valve containment assembly which is designed as an extension of the containment boundary. These valves are inaccessable during. plant operation. The valves can be made accessable during plant shutdown by disassembly of the valve containment assembly. This requires approximately 100 man-hours per valve in a radiation field up to 50 mr per hour. Verification that the valve position indication switches have changed in relation to valve position can be made by ob-serving that no significant change in valve stroke time has occurred. Due to the burden in manpower and radiation exposure to perform the direct observation, relief is taken from the requirements of IWV-3000. 27) These valves can only be full stroke tested by rendering their control systems inoperable. These valves will be full stroke tested during cold shutdown. 32? 151 Page 8 3 of 8 3

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