ML19269D192

Inservice Testing & Insp Program, Suppl 3

ML19269D192
Person / Time
Site:	Indian Point
Issue date:	02/28/1979
From:	CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To:
Shared Package
ML19269D189	List: ML19269D188 ML19269D192
References
PROC-790228, NUDOCS 7903070247
Download: ML19269D192 (52)

Text

.

O INDIAN POINT NUCLEAR GENERATING UNIT NO.'2 (Docket No. 50-247)

INSERVICE INSPECTION AND TESTING PROGRAM Supplement No. 3 Consolidated Edison Company of New York, Inc.

Februnri, 1070 7903 070,7f}

w-Supplement No. 3 Instruction Sheet Remove the old pages and insert the new pages into the Indian Point Unit No. 2 Inservice Inspection and Testing Program as follows:

Remove Insert pgs. 1 through 7 pgs. 1 through 8 El-1, El-2, El-3, El-4 El-1, El-2, El-3, El-4 El-d, El-ll, El-12, El-13, El-8, El-ll, El-12, El-13 El-15, El-16 El-15, El-16, El-17 E2-1, E2-2, E2-3, E2-4 E2-1, E2-2, E2-3, E2-4 E2-6, E2-8, E2-9, E2-13 E2-6, E2-8, E2-9, E2-13 Enclosure 5 title page Enclosure 5 title page E5-1 through ES-4 ES-1 through ES-7 Figure E5-1 Figures ES-1 & ES-2 Enclosure 6 title page Enclosure 6 title page E6-1 through E6-9 E6-1 through E6-12 Supplement 3 Feb. 1979

x_ -

Indian Point Nuclear Generating Unit No. 2 Inservice Inspection and Testing Program INTRODUCTION The inservice inspection and testing program described herein has been developed as required by Section 50.55a of 10 CFR Part 50 as amended February 1976.

APPALICABILITY This inservice inspection and testing program is applicable to the:

a. Inservice inspection of Quality Group A, B and C systems and com-tonents (and their supports) for the unit's second forty month

.nspection period of the first ten year inspection interval (November 1, 1977 through February 28, 1981).

b. Inservice testing of Quality Group A, B and C pumps and valves for the unit's third twenty month inspection period (November 1, 1977 through June 30, 1979) and fourth twenty month inspection period (July 1, 1979 through February 28, 1981) of the first ten year inspection internal. 3_

APPLICABLE CODES In accordance with Section 50. 55a (g) of 10CFR Part 50, the applicable ASME B&PV Code Section XI, Division 1, edition and addenda for the inspection periods specified above are the:

a. 1974 edition with addenda through Summer 1975 for the inservice inspection of Quality Group A, B and C systems and components (and their supports).

b. 1974 edition with addenda through Summer 1975 for the inservice testing of Quality Group A, B and C pumps and valves. Il SYSTEM AND COMPONENT CLASSIFICATION Quality Group criteria for the classification of systems and compo-nents of Indian Point Unit No. 2 are consistent with NRC Regulatory Guide 1.26, Revision 3.

PROGRAM DESCRIPTION Enclosures 1, 2, and 3 identify specific components and parts to be examined in accordance with subsections IWB, IWC and IWD for Quality' Group A, B and C examinations, respectively. Enclosure 4 provides information concerning the withdrawal of materials irradiation sur-veillance specimens from the Indian Point Unit No. 2 reactor vessel.

Enclosures 5 and 6 identify specific Quality Group A, B and C pumps and valves to be tested in accordance with subsections IWP and IWV, 1

Enclosures tor the inservtce inspection of guality Group A, B, and C components identify the components to be inspected, the component 1 Supplement 3 Feb. 1979

Quality Group classification, the applicable code to which the component was fabricated and the method of examination. Where these inspection re-Iuirements have been determined to be impractical, the enclosures identi-fy the applicable code requirement, justification for the exception taken, and where practical, the inspection method to be used as an alternative.

Enclosure 5 provides a listing of the Quality Group A, B, and C pumps subject to the inservice testing requirements of subsection IWP. The pumps are those provided with an emergency power source which are re-lied upon to fulfill the safety-related function of safely shutting down the reactor or of mitigating the consequences of a postulated accident. The enclosure identifies the pumps to be tested, pump Quality Group classification, parameters to be measured or observed, and test intervals. Where these inspection requirements have been determined to be impractical, the enclosure identifies the applica-ble code requirement, justification for the exception taken, and where practical, the inspection method to be used as an alternative.

Similatly, Enclosure 6 provides a listing of the Quality Group A, B and C valves subject to the inservice testing requirements of subsection IWV. The enclosure identifies the valves to be tested, the Section XI category as defined by INV-2000, and test frequencies. Exception to the Section XI specified testing requirements is taken in cases where these requirements have been determined to be impractical. In such instances, the enclosure identifies the applicable code requirement, justification for the exception taken, and where practical, the inspec-tion method to be used as an alternative. This valve testing program has been reviewed to ensure that testing of valves at the intervals specified will not place the plant in an unsafe condition. y The inservice inspection and testing program outlined in the attached enclosures has been developed following a design review. Should 5 3 certain ASME B&PV Code Section XI requirements be discovered to be impractical due to unforeseen circumstances during the process of performing inspections or tests, such situations, including the rea-sons for impracticality, shall be documented.

Access Considerations Indian Point Unit No. 2 was designed and constructed prior to the incep-tion of the ASME B&PV Code Section XI. Consequently, some examinations may be limited due to considerations of design, access or materials of construction. Radiation levels in certain areas or of certain components may also restrict the access to perform examinations or tests. In such instances, the examinations or tests will be performed to the extent practical.

Acceptance Standards Evaluation of indications detected in Quality Group A, B and C compo-nents, exceeding specified threshold levels for evaluation, during inservice examinations, will be made using the acceptance standards for materials and welds specified in the code under which a,ra the component 1, g , 3 , ya . t,.

it -

--- c u- n n c e3n 2 Supplement 3 Feb. 1979

applicable Section XI edition and addenda or other analyses determined suitable by Con Edison Engineering may be used.

Repair Procedures When evaluation of indications detected during inservice examinations of Quality Group A, B and C components indicate the need for repair, procedures shall be developed in accordance with the applicable section XI edition and addenda or, alternatively, in accordance with the Con Edison Quality Assurance Program l in effect at time of repair.

Fabrication Codes Codes referenced as being applicable to the fabrication of components are:

III A ASME B&PV Code,Section III, Class A Nuclear Vessels.

III C ASME B&PV Code,Section III, Class C Nuclear Vessels.

VIII ASME B&PV Code,Section VIII, Pressure Vessels.

B31.1 USA Standard USAS B31.1 Code for Pressure Piping.

B16. 5 USA Standard USAS B16.5 Steel Pipe Flanges , Flanged Valves and Fittings.

AWWA, American Water Works Association D100-65.

D100-65 Ultrasonic Examination When required, ultrasonic examination will be performed, to the extent practical, in accordance with the applicable requirements of ASME B&PV Code Sactions V or ; with the following stipulation in lieu of code requirements:

(1) Ultrasonic examination indications detected in piping and vessel welds which produce a response greater than 75% of the reference level shall be recorded.

(2) Ultrasonic examination indications detected in piping and vessel welds which produce a response greater than 100% of the reference level shall be investigated to the extent that the operator can determine the shape, identity and location of the indication for evaluation with respect to the applicable acceptance criteria.

The ultrasonic techniques and procedures to be employed for the inserv- -

ice examination of Quality Group A and B piping and pressure vessel 5 3

welds sh'all be technically equivalent to the requirements of the Code Section V or XI rules. Techniques and procedures in all cases may not necessarily adhere to all the specific requirements of the code rules.

Nondestructive examination, equipment, procedures and techniques, al-ready established and implemented to support prior plant Technical Specification commitments to ASME B&PV Code Section XI, need not 1 The later" re"4-icr *o *"" P^" "'4"*" ^"7 14*" ^"m1" anon Proaram dated Jur 3, 1~~i, -

3 Supplement 3 Feb. 1979

L-necessarily be revised unless Con Edison Engineering or Quality Assur-ance determines that a necessary and substantial benefit would result from such revision.

Ultrasonic examination techniques which are referenced or included in editions and addenda of Code Sections V or XI subsequent to the edi-tions and addenda applicable to this inspection period may be used.

Where calibration block material specification equivalence is required, material specification equivalence shall be established by "P" number grouping in lieu of the requirements of paragraph I-3121 or other similar code requirements. "P" numbers are given in ASME B&PV Code Section VIII.

Delays due to malfunctions of the automated reactor vessel inspection tool, although infrequent, have been experienced. When malfunctions occur, timely repairs will be initiated. However, during vessel in-spections which do not require removal of reactor internals and thermal shield, if the malfunctions are anticipated to preclude completion of the inspections within twenty four hours beyond the expected forty eight hours required, activities will be discontinued and the remaining examinations rescheduled for the subsequent inspection period.

Rescheduling of planned examinations will not significantly alter the overall reactor vessel inspection program since it would only delay the planned inspections while still assuring that all reactor vessel inspec-tions are performed within the ten year inspection interval as required by Section XI. The resultant reactor vessel inspection sequence, al-though differing from the exact schedule proposed by Section XI, will be consistent with the intent of Section XI; that is, to provide mean-ingful inspections without undue delay in plant operation.

Item / Area Identification and Datum Reference Markings At the time of construction of Indian Point Unit No. 2, application of item / area identification and datum reference markings was not required.

Application of such markings to each and every item or area subject to examination is deemed impractical for an operating plant. In many instances, no physical access is available to permit such marking. In other instances, exposure levels prohibit their application. Datum points will however be established in the event that recordable indi-cations are to be reported. Such datum points shall either be marked on the component (s) or have their location (s) adequately described such that subsequent relocation can be achieved within 0.5 inches.

Accordingly, exception is taken to the marking requirements of Appen-dix I, I-6230 and all such similar requirements for the marking of piping, vessels, pumps and valves.

System Pressure Tests

1. Requirements for the visual examination of Quality Group A sys-tems and components for evidence of leakage during the performance of (a) a system leakace test prior to start-up followina each 7

i ,. .

at .._i. Aud 4 Supplement 3 Feb. 1979

by IWB-5200, are impractical on those portions of Quality Group A systems which are contained between two check valves or two nor-mally cloced valves where pressure applied to the reactor coolant system will be retained at the first valve in the line. Portions of systems affected by this limitation are:

(a) RHR suction line between MOV-731 and MOV-730.

(b) RCS loop drains between normally closed valves 505A & B, 508A & B, SllA & B, and 515A & B.

(c) Pressurizer auxiliary spray line (CVCS) between check valves 211 and 374.

(d) Charging line to RCS loop 21 cold leg between check valves 210B and 374.

(e) Charging line to RCS loop 22 hot leg between check valves 210A and 374.

(f) Seal injection lines between check valves 251 A, B, C& D and 251E, F, G& H.

2. Subsections IWB and IWC contain d#ffering requirements for the hydrostatic testing of Quality Group A and B systems and compo-nents. The implementation of these requirements is impractical

. when the only means of pressurizing the Quality Group B system is through the Quality Group A system or when the boundary between the two systems is a check valve arranged for flow from the Quali-ty Group B system to the Quality Group A system. Performance of hydrostatic tests as required by IWC-2412 (a) and IWC-5000 is impractical where such limitations exist. Portions of Quality Group B systems affected by this limitation are identified below.

Visual examination for ev.idence of leakage will be conducted on these portions at pressures compatible with the pressure test requirements for the adjoining Quality Group A system, to the extent practical.

(a) R.C. pump seal bypass lines from the flow orifices to air operated valve 246.

(b) R.C. pump seal leak-off lines to manual valves 243A, B, C

& D and 244A, B, C& D.

(c) R. C . pump seal injection lines from check valves 251E, F, G and H to manual valves 250A, B, C and D.

The potential for inadvertent overpressurization of the reactor coolant system precludes the advisability of pressurizing Quality Group B systems to considerably higher pressures than the adjacent Quality Group A system. Implementation of the hydrostatic test requirements of IWC-2 412 (a ) and IWC-5000 on the CVCS system where 5 Supplement 3 Feb. 1979

such pot ntial exists is therefore considered impracticai. The chemicaJ and volume control charging, seal injection and letdown systems are in continuous operation during normal plant operation and are continuously monitored to ensure continued integrity and performance.

The pressure tests and associated visual examination requirements of IWC-2 412 (b) and IWC-5000 are impractical for the Quality Group B portions of the RHR system between motor operated valves 746 &

747 and check valves 83SA, B, C& D. Flow direction check valves preclude pressurization from the reactor coolant system and pres-strization using the RHR or recirculation pumps cannot be &ccom-plished at the required pressures. These segments will be examined for evidence of leakage at pressures consistent with adjacent segments of the RHR system.

Hydrostatic testing of the RHR syste, is currently performed in accordance with Technical Specification requirements. The pressures specified for RHR system hydrostatic testing provide adequate margin above the highest pressures e::pected within the system after a design basis accident. Hydrostatic tests of the RHR system will continue to be performed in accordance with section 4.4 cf the plant Technical Specifications.

The pressure test and visual examination requirements of IWC-2412 (a) and IWC-5000 are unnecessary with respect to the Accumu-lators and the Boron Injection Tank. These vessels are maintained under nitrogen blanket overpressures during all modes of normal reactor operation and are continuously monitored to ensure continued integrity and performance.

Th'e pressure test and visual examination requirements of IWC-2412(a) with respect to steam generator blowdown and blowdown sample lines are considered impractical as these lines can only

~be pressurized in conjunction with pressurization of the steam --

generator secondary side. Hydrostatic testing of these lines will be performed in conjunction with the steam generator secondary side at intervals specified by IWC-2412 (b) .

Quality Group B piping systems contained between containment iso-lation valves which cannot be pressure tested with adjoining systems will be tested in accordance with 10CFR Part 50, Appendix J, and unit technical specification requirements for containment isolation valves (Type C Testing) .

3. The' examination requirements for Quality Group C systems and com-ponents as presented in Enclosure 3 are in accordance with IWD-2410 (c) which specifies that 100% of the components be examined as required by IWA-5240 and IWD-2600 either during system in-service testing or during normal plant operation. An additional requirement of IWD-2410 (b) is the examination of Quality Group C systems and components for evidence of leakage during the perfor-mance of a system hydrostatic pressure test in accordance with IWD-

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6 Supplement 3 Feb. 1979

should be noted that these system pressure tests are impractical in those systems such as component cooling, service water, spent fuel pit cooling and boric acid transfer and recirculation, which are typically in continuous operation during all modes of plant operation. The continuous ft.netional operation serves to demon-strate the structural integrity and performance of these systems.

Where access to this piping is available, visual examinations for evidence of leakage will be performed on these systems during normal plant operation to verify leak-tightnese.

4. Portions of piping systems that cannot be pressurized or pres-surized to the specified pressures, either through the reactor coolant system or by installed equipment, will not be pressurized unless provisions for connecting an external pressure source and adequate isolation capability currently exist.

5. Where overpressure protection is provided for normal plant opera-tion, test pressures shall not exceed the limits or set points established for normal plant operation or the pressures specified by Section XI, whichever is less.

6. Where the hydrostatic test pressure and temperature requirements of Section XI may potentially degrade the operability or integrity of piping systems or components, the pressures and temperatures shall be revised appropriately.

~

Personnel Qualifications Personnel performing nondestructive examination involving ultra-sonic, radiographic, eddy current, magnetic particle or liquid pene-tran', techniques shall be qualified with a procedure prepared in accordance with SNT-TC-1A for the applicable examination technique and methods as required by IWA-2300. Other personnal, such as those performing visual examination for evidence of leakage duting system pressure tests or who monitor contractor activities, are typically members of the onsite operating organization and as such are qualified as described in the Con Edison Quality Assurance Program in effect at time of inspection.

Authorized Inspector As an alternate to requiring an Authorir.ed Inspector to document, witness, veri fy, approve etc. , inservice inspections, tests and re-pairs to Quality Group A, B and C systems and components, verifica-tion of the adequacy of these activities will be accomplished as described in the Con Edison Quality Assurance Program in effect at time of inspection, test or repair. This program provides for:

a. The review by Quality Assurance and Reliability of nondestruc-tive examination tecnniques and methods as well as the qualifi-cations of personnel performing nondestructive examinations.

b. A vendor qualification process.

7 Supplement 3 Feb. 1979

c. Monitoring by the Quality Assurance Engineer (NPG) to assure compliance with approved procedures.

dditionally the Authorized Inspector will be utilized to verify the adequacy of repairs to all ASME B&PV Code Section III stamped pres-sure vessels. This approach is consistent with current New Yor:<

State law which does not invoke Section XI of the ASME B&PV Code as part of it's boiler and pressure vessel requirements.

Reporting Requirements The reporting requirements of IWA-6220 (b) require filing of inservice inspection reports within nincty days after completion of the inser-vice inspection with the regulatory authority having jurisdiction at the plant site. Results of previous preservice and inservice exami-nations indicate the time required to compile, edit, review and evaluate the large quantities of documentation involved often exceeds the ninety day reporting requirement. Should scheduling conflicts develop, such that report submittal cannot be accomplished as re-quired by IWA-6220 (b) , the NRC will be notified. The " Owner's Data Report" required by IWA-6220(e) shall not form a part of the report submittal required by IWA-6220 (b) .

! 3.

8 Supplement 3 Feb. 1979

INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 INSERVICE INSPECTIGN PROGRAM - QUALITY GROUP A COMPONENTS I. WB 2< > 2500 I' -: EXAM. SYSTEM OR FAB. AREA TO BE EXAMINATION SECTION XI 1: . CAT. COMPONENT CODE EXAMINED REQUIREMENT CODE RELIEF B1 .1 B-A Reactor Vessel III A Longitudinal and cir- Volumetric No - Note 1 33 cumferential shell welds in core region l' . B-B Longitudinal and cir- Volumetric Yes - Note 2 cumferential welds in shell (other than those of category B-A and B-C) and meridional and circumferential seam welds in bottom head and closure head (other than those of category B-C)

? B-C " " " Vessel to flange and Volumetric No - Note 3 head to flange cir-cumferential welds 1 B-D " " " Primary nozzle to Volumetric No - Note 4 vessel welds and nozzle inside radiused section

.3 B-E " " " Vessel penetrations, Visual No - Note 5 including control rod (IWA-5000) drive and instrumenta-tion penetrations El.6 B-F " " "

Nozzle to safe end Volumetric Yes - Note 6 welds El-1 Supplement 3 Feb. 1979

INDIAN POINT NUCLEAR "ENERATING UNIT NO. 2 INSERVICE INSPECTION PROGRAM - uUALITY GROUP A COMPONENTS a IWB l 10 2500

M EXAM. SYSTEM OR FAB. AREA TO BE EXAMINATION SECTION XI 6

CAT. COMPONENT CODE E XAMINED REQUIREMENT CODE RELIEF

' .7 B-G-1 Reactor Vessel III A Closure studs, in place N/A Yes - Note 7 1' .8 B-G-1 Closure studs and nuts, Volumetric Yes - Note 8 when removed & Visual

.9 B-G-1 Ligaments between Volumetric No - Note 9 threaded stud holes

.10 B-G-1 Closure washers, Visual No - No te 10 bushings

.11 B-G-2 P re s s ure-re tainin g Visual No - Note 11 bolting

.12 B-H Integrally welded N/A No - Note 12 1 vessel supports

.13 B-I-l Closure head cladding N/A Yes - Note 13 l .14 B-I-l Vessel cladding N/A Yes - Note 13 i

.15 B-N-1 Vessel In te rior Visual No

.16 B-N-2 Interior attachments N/A No - Note 14 E 3 and core support structures ,

.17 B-N-3 Core support structures Visual No

.18 B-O Control rod drive Volumetric No - Note 15 housings El-2 Supplanent 3 Feb. 1979

f INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 INSERVICE INSPECTION PROGRAM - QUALITY GROUP A COMPONEiiTS IWB 0 2500 Si EXAM. SYSTEM OR FAB. AREA TO BE EXAMINATION SECTION XI CAT. COMPONENT CODE EXAMINED REQUIREMENT CODE RELIEF 19 B-P Reactor Vessel III A Exempted components Visual No (IWA-5000)

.1 B-B Pressurizer III A Longitudinal and cir- Volumetric Yes - Notas 16, cumferential welds 17 2 B-D Nozzle to vessel welds N/A No - Note 18 and nozzle inside radiused section

.3 B-E Heater penetrations Visual No - Note 19 (IWA-5000) 4 B-F Nozzle to safe end Volumetric Yes - Note 47, welds & Surface 50 3

.5 B-G-1 Pressure-retaining N/A No - Note 20 bolts & studs, in place

.6 B-G-1 Pressure-retaining N/A No - Note 20 bolts & studs, when removed

.7 B-G-1 Pressure-retaining N/A No - Note 20 '

bolting

'.3 B-H Integrally welded Volumetric No - Note 21 vessel supports \

.9 B-I-2 Vessel cladding N/A Ye s - No te 13 El-3 Supplement 3 Feb. 1979

INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 INSERVICE INSPECTION PROGRAM - QUALITY GROUP A COMPONENTS

IWB

. 1 2500

'4 EXAM. SYSTEM OR FAB. ARE A TO BE EXAMINATION SECTION XI

. CAT. COMPONENT CODE EXAMINED REQUIREMENT CODE RELIEF i'.10 B-P Pressurizer III A Exempted components Visual (IWA-5000)

No 11 B-G-2 " " Pressure-retaining Visual No - Note 22 bolting Steam Generators III A Longitudinal and cir- Volumetric No - Notes 23,

,1 B-B (4) (Primary cumferential welds , 24 Side) including tubesheet to head or shell welds on the primary side

.2 B-D Nozzle to head welds N/A No - Note 25 and nozzle inside radiused section on the primary side 3 B-F Nozzle to safe end Volumetric Yes - Note 50 5 3 welds & Surface 4 B-G-1 Pressure-retaining N/A No - Note 26 bolts & studs, in place

.5 B-G-1 Pressure-retaining N/A No - Note 26 bolts & studs, when removed

.6 B-G-1 Pressure-retaining N/A No - Note 26 bolting Supplement 3 El-4 Feb. 1979

I INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 INSERVICE INSPECTION PROGRAM - QUALITY GROUP A COMPONENTS I: IWB

) 2500

~1 EXAM. SYSTEM OR FAB. AREA TO BE EXAMINATION SECTION XI CAT. COMPONENT CODE EXAMINED REQUIREMENT CODE RELIEF 1 B-G-1 Piping B31.1 Pressure-retaining N/A No - Note 30 Pressure bolts & studs, when Boundary removed B-G-1 Pressure-retaining N/A No - Note 30 I. i bolting Circumferential & Volumetric Yes - Notes 33,

> B-J longitudinal pipe welds 34, 35, 47, 48, 50 l

33 l' o B-J Branch pipe connec- Volume tric Yes - Note 36, l-tion welds exceeding 50 g3 6 inch diameter I 7 B-J Branch pipe connec- Surface No tion welds 6 inch diameter and smaller 1 B-J " "

Socket welds Surface No 1; ) B-K-1 Integrally welded Volumetric Yes - Note 37, supports & Surface 49 g3 10 B-K-2 Support components Visual No

/

Is L1 B-P Exempted components Visual No f (IWA-5000)

I- 12 B-G-2 " "

Pressure-retaining Visual No - Note 38 bolting El-8 Supplement 3 Feb. 1979

NOTES-QUALITY GROUP A COMPONENTS L. Due to the Indian Point Unit No. 2 plant design, the welds in the reactor vessel are not accessible f rom the O. D. These welds will be volumetrically examined from the I.D. using remote mechanized techniques. Since the examination of these welds re-quires removal of the core internals and thermal shield, the examinations are sched-uled near the end of the ten-year inspection interval.

?. The closure head peel segment to disc circumferential weld is completely enclosed within the pattern of the CRDM penetrations inside the shroud and as such is not accessible for volumetric examination as required by IWB-2600. The area will be visually examined for evidence of leakage during the performance of system hydrostatic tests. A small portion of the meridional welds in the closure head between the headwhen flange and the the head is CRDM shroud are accessible for ultrasonic examination from the O.D.

removed from the vessel. Volumetric examination of the bottom head peel segment meridional welds and the bottom head peel segment to disc circumferential weld as required by IWB-2600 is restricted fromVisual insideexamination the vessel for by the location of adjacent evidence of leakage in-core instrumentation penetrations.

during the performance of system hydrostatic tests will be performed from the area ,

below the vessel to the extent practical as personnel exposure levels permit. Welds accessible to the remote inspection device will be volumetrically examined from the I.D.

The head-to-flange weld will be examined using manual ultrasonic techniques. This weld is accessible when the head is removed for refueling. Due to plant design, the vessel to flange wcld in the reactor vessel is not accessible from the O.D. This weld will be volumetrically examined from the I.D. using remote mechanized techniques.

Due to plant design, the vessel nozzle welds are accessible only from the I.D. The 53 inner radius of the outlet nozzles can be volumetrically examined, using remote mechanized techniques, without removing the core barrel. However, the core barrel must be removed to examine the inlet nozzles. For this reason, it is planned that the examination of the outlet nozzles be performed during the planned refuel-ing outages near the end of the first and second forty month inspection periods and the inspection of the inlet nozzles near the end of the third forty month in-spection period (end of ten-year inspection interval).

The CRDM seal welds, CRDM and instrumentation penetrations and vent connection weld to the closure head, as well as the instrumentation penetration welds to the bottom El-11 Supplement 3 Feb. 1979

head are included in this category. The required number of penetrations, of each group of penetrations of comparable size and function will be visually examined for evidence of leakage during the performance of system pressure tests, to the extent practical, as permitted by personnel exposure levels.

6. There are dissimilar metal welds between the carbon steel nozzle forgings and the tainless steel transition (spool) pieces of the reactor coolant piping. These welds will be volumetrically examined during the inspection interval. The examinations will conincide with the item 1.4 examinations of primary nozzle to vessel welds and nozzle inside radiused section (reactor vessel). Surface examination of these welds from the I.D. is impractical. Limited access to the O.D. of these welds is provided by removeable plugs in the primary shield above the nozzles. However, fixed non-removeable insulation about the nozzle / pipe circumference precludes examination by any method requiring physical surface contact. Exception is taken to performing a surface exami- 3 nation on these welds due to anticipated radiation levels and physical access. Indi-rect visual examination for evidence of leakage during the performance of system hydro-static tests will be performed to the extent practical, considering personnel exposure Levels.

rhe reactor vessel closure studs are removed during each refueling and there will be no need for examination in place as required by IWB-2600.

Iolumetric examination of closure studs and nuts, when removed will be performed as required by IWB-2600. Exception is taken to performing surface examination of closure

tud and nut threaded areas due to thread root geometry and the inability to insure complete removal of all traces of thread compound which could interfere with examina-tion results. Visual examination will augment the volumetric exanination.

rhis examination is applicable to the vessel flange only as the closure head flange aoles are not threaded.

1 chere are no closure bushings associated with the reactor vessel.

li 'Che only pressure re taining bolting smaller than two inch diameter associated with the reactor vessel is the conoseal bolting.

1: rhere are a total of four vessel-support pads welded to inlet and outlet nozzles on the Indian Point Unit No. 2 vessel. In accordance with category B-H of IWB-2500, the area to be examined is the welded connection between the nozzle and vessel shell.

This examination is covered by item 1.4, primary nozzle to vessel welds and nozzle inside radiused section (reactor vessel).

El-12 Supplement 3 Feb. 1979

1 :xception is taken to performing vessel cladding examinations. The cladding's intended function is to minimize corrosion products, not to provide structural support. The surface areas involved in these examinations are insignificant to the total clad surface area and are typically high exposure examinations. This position is consistent.with the latest Section XI code addenda in which cladding examinations nave been deleted.

1/ This requirement is applicable to boiling water reactors only.

1- Et is believed that a small number of peripheral control rod drive mechanisms are iccessible through cut-outs in the CRDM shroud. Access, joint geometry and exposure levels permitting, the required number of welds in peripheral CRDM housings will be volumetrically examined to the extent practical.

l' rhe upper circumferential and longitudinal welds in the pressurizer are enclosed in a biological and missile shield and are therefore not accessible for volumetric 3xamination as required by IWB-2600. Indirect visual examination for evidence of leakage during system hydrostatic tests will be performed to the extent practical.

xamination of accessible portions of pressurizer longitudinal and circumferential welds below the operating deck will be performed as required by IWB-2600.

1. The pressurizer inclusion area is located in, and adjacent to the heat affected zone of longitudinal weld PZRL-2. Ultrasonic examination of this area will be performed 3 during refueling outages. Should these examinations indicate no change in inclusion oattern after the second refueling outage examination, the examination requirements of the ASME Section XI code may subsequently be followed, provided this inclusion area is included as part of Category B-B examination requirements (Table IWB-25 00) .

(Note: The second refueling outage examination has been completed with no change in inclusion pattern observed, future examinations will be performed as noted above) . 3 1 The nozzles on the pressurizer are cast with the upper and lower heads; therefore, no inspections are required for this item number.

1 Pressurizer instrument and thermocouple penetrations are included in this category as well as heater penetrations. Visual examination for evidence of leakage will be /

performed during system pressure tests as required by IWB-2600.

I

20. There is no pressure retaining bolting 2 in. diameter or greater associated with the (

pressurizer.

21 The only integrally welded support associated with the pressurizer is the weld attach-ing the support skirt to the lower head. Volumetric examination will be performed as required by IWB-2600.

El-13 Supplement 3 Feb. 1979 .

2xaminations cannot bc performed as required by IWB-2600. These welds will be subject to visual examinaticn for evidence of leakage during system hydrostatic tests. These telds are the only longitudinal welds.in the reactor coolant loop piping.

34. he circumferential butt welds attaching the reactor coolant pipe to the 15 and 28 legree elbows in the cold legs are completely enclosed within the biological shield and are therefore not accessible for volumetric examination as required by IWB-2600.

Indirect visual examination for evidence of leakage during the performance of system hydrostatic tests will be performed to the extent practical.

35. The circumferential butt welds attaching the stainless steel transition (spool) pieces an the reactor vessel nozzles to the reactor coolant piping will be examined from the nozzle bores using remote mechanized ultrasonic techniques. Access to approxi-mately 25% of the outside surface circumference of these welds is provided through removable plugs in the biological shield; however, removable insulation has not been provided and no examinations are planned from the O.D. o f t'.tese welds. Volumetric 3 2xamination of these welds will be performed in conjunction with item 1.4 - Primary nozzle to vessel welds and nozzle inside radiused section (reactor vessel).

3* "h e geometric configuration of the weld surface may prevent ultrasonic examinations

' rom being performed to the extent required by IWB-2600. Examinations will be per-

'ormed to the extent practical from the pipe and nozzle surfaces adjacent to the weld.

urface examination of the weld may be performed, as necessary to supplement the folumetric examination.

3 ?he piping system integrally welded supports are attached to the pipe by fillet welds.

?he configuration of such welds is such that examinations cannot be performed to the 2xtent required by IWB-2600 and only the base material of the pipe wall can be examined by ultrasonic techniques. Surface examination will be performed on integrally welded ittachments to supplement the volumetric examination.

3 :- Phe only pressure retaining bolting less than two inch diameter in the piping boundary is at the flanged connections joining the upstream side of the three pres-surizer sa fe ty valves to the relief line.

39 The only pressure retaining bolting associated with the reactor coolant pumps two inch diameter or greater is the main flange botting.

40. Volumetric examination of reactor coolant pump main flange bolting will be performed as required by IWB-2600. Exception is taken to the surface examination of threaded El-15 Supplement 3 Feb. 1979

areas due to thread root geometry and the inability to ensure the removal of all ,

traces of thread lubricants which could interfere with examination results.

41. Volumetric and surface examinations of reactor coolant pump main flange bushings, threads and ligaments in base material is impractical due to component geometries and materials of construction. These component parts will be examined in accordance with the examination requirements of item 5.7 (reactor coolant pumps) .

42. The reactor coolant pump supports consist of a cast foot welded to the pump casing (three supports per pump) . There are no currently known techniques for ultrasonically

. examining these welds. Surface examination is substituted.

4- The reactor coolant pump casing is a weldment of two cast shells. At this time, there are no proven means of volumetrically examining the pump casing welds in service and therefore no examinations are planned. New NDE techniques will be evaluated for application on the pump casing welds and consideration given to performing volumetric examination as techniques become available.

4 Reactor coolant pump main flange bushings, threads and ligaments in base material are subject to these examinatien requirements (see note 41).

4 The only pressure retaining bolting associated with the reactor coolant pumps less than two inch diameter is the seal house bolting.

4- Each reactor coolant pump flywheel will be subject to an in place visual and volumet-ric examination of the areas of higher stress concentration at tha bore and keyway by the end of the first and second forty month inspection periods. A complete in place visual and volumetric examination of each flywheel will performed at or near the end of the ten-year inspection interval.

4 The arrangements and details of the piping systems and components are such that some examinations as required by IWB-2600 are limited due to geometric configuration of accessibility. Generally, these limitations exist at pipe to fitting welds, where examination can only be fully performed from one side; the fitting geometry limiting or even precluding examination from the opposite side. Welds having such restric- ,

tions will be examined to the extent practical. When not otherwise required, sur-face examinations may be utilized to augment volumetric examinations where practical. 3 4 In instances where the location of pipe supports or hangers restrict the access available for the examination of pipe welds as required by INB-2600, examinations will be performed to the extent practical.

El-16 Supplement 3 Feb. 1979

49. Applicable construction codes required only visual examination of integral support welds. During inservice inspection, surface examination will be employed and indi-cations previously accepted by visual examination may require further evaluation.

Such indications will be evaluated in accordance with the as-constructed codes.

Minor surf ace indications resulting from the original welding process which are de-termined not to be cracks or lack of fusion and not service connected will not require further action. These indications will not adversely affect overall weld integrity as evidenced by the satisfactory performance of these welds to date.

51. The piping system welds were constructed in accordance with, and satisfied the re-quirements of, the codes and specifications applicable at the time of construction.

The integrity of these welds has been further verified by satisfactory performance during plant operation. The original fabrication codes and specifications did not require ultrasonic examination of welds. Conditions such as high and irregular weld crowns or rough surface finish may limit ultrasonic transducer contact to less than that required to completely scan the examination volume. In such instances, examinations will be performed to the extent practical consistent with these limita-tions. Such conditions shall b'e identified and documented in the examination results. 3 El-17 Supplement 3 Feb. 1979

INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 INSERVICE INSPECTION PROGRAM - QUALITY GROUP B COMPONENTS

' :C IWC 400 2500

?EM EXAM. SYSTEM OR FAB. AREA TO BE EXAMINATION SECTION XI i :0. CAT. COMPONENT CODE EXAMINED REQUIREMENT CODE RELIEF

! '.1 C-A Steam Generators III C Circumferential butt Volumetric Yes - Notes 1, l2,3 (4) (Shell Side) welds 31 Volumetric Yes - Notes 2,

't.2 C-B Nozzle to vessel welds 31 [2'3

" " -" No - Note 3

.3 C-C Integrally welded N/A supports Pressure-retaining Visual & Yes - Notes 4,

, 'L.4 C-D bolting either Sur- 31 l2.'3 face or Volu-metric III C Circumferential butt Volumetric Yes - Notes 12,

-.1 C-A Residual IIcat Exchangers (2) welds 31 l2'3 (Tube Side)

' i. 2 C-B Nozzle to vessel Volumetric Yes - Notes 5, l2 welds 31

.L.3 C-C Integrally welded Surface Yes - Notes 6, [ 2,3 suoports 31 Pressure-retaining Visual Yes - Notes 7,

-.4 C-D bolting & either Sur- 31 l2'3 / '

j face or Volu- (

! metric

1.1 C-A Volume Control III C Circumferential butt Volumetric No - Notes 8, Tank (1) welds 19 Supplement 3 E2-1 Feb. 1979

INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 INSERVICE INSPECTION PROGRAM - QUALITY GROUP B COMPONENTS IE IWC 2r 2500 Ir EXAM. SYSTEM OR FAB. AREA TO BE EXAMINATION SECTION XI CAT. COMPONENT CODE EXAMINED REQUIREMENT CODE RELIEF C1 C-B Volume Control III C Nozzle to vessel Visual (IWA- No - Notes 9, 19 Tank (1) welds 5000)

CJ C-C Integrally welded Surface Yes - Notes 10, suoports 19, 32 3 C C-D Pressure-retaining Visual & No - Notes 11, bolting either Sur- 19 face or Volu-metric C! C-A Seal Water Heat III C Circumferential butt Surface & Yes - Notes 13, Exchanger (1) welds Visual 17 (Tube Side)" "

C1 C-B Nozzle to vessel Visual (IWA- No - Notes 9, 14 welds 5000)

Cl C-C Integrally welded N/A No - Note 3 supports C2 C-D Pressure-retaining N/A No - Note 3 bolting C! C-A Non-Regenerative III C Circumferential butt Volumetric No - Note 15 Heat Exchanger (l) welds (Tube Side)" "

CJ C-B Nozzle to vessel Visual (IWA- No - Notes 9, 16 welds 5000) [

E2-2 Supplement 3 Feb. 1979

INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 INSERVICE INSPECTION PROGRAM - QUALITY GROUP B COMPONENTS i

It IWC 2t 2500 IC EXAM. SYSTEM OR FAB. AREA TO BE EXAMINATION SECTION XI I: CAT. COMPONENT CODE EXAMINED REQUIREMEFT CODE RELIEF C2 C-C Non-Regenerative III C Integrally welded N/A No - Note 3 Heat Exchanger (1) supports (Tube Side)" "

Ci C-D Pressure-retaining N/A No - Note 3 bolting Cl C-A Reactor Coolant III C Circumferential butt Surface & Yes - Notes 17, Filter (1) welds Visual 18, 19 C C-B Nozzle to vessel Visual (IWA- No - Note 9 welds 5000)

C C-C Integrally welded Surface Yes - Notes 19, supports 20, 32 ,

I3 C C-D Pressure-retaining N/A No - Note 3 bolting C: '

C-A Seal Water III C Circumferential butt Volumetric Yes - Notes 19, welds 21,31 Iniection Filters (27" l2 C C-B Nozzle to vessel Visual (IWA- No - Note 9 welds 5000)

C -' C-C Integrally welded Surface Yes - Notes 19, supports 22,31,32 l 2,3 '

l Cl.. C-D Pressure-retaining Visual & Yes - Notes 19, bolting either Sur-face or Volu-31 l2 i metric E2-3 Supplement 3 Feb. 1979

INDIAN POINT NUCLEAR" GENERATING UNIT NO, 2 INSERVICE INSPECTION PROGRAM - QUALITY GROUP B COMPONENTS IL IWC 2 / 2500 I EXAM. SYSTEM OR FAB. AREA TO BE EXAMINATION SECTION XI

': . CAT. COMPONENT CODE EXAMINED REQUIREMENT CODE RELIEF C2.1 C-A Seal Water Return III C dircumferential butt Surface & Yes - Notes 17, Filter (1) welds Visual 19, 23 Cl C-B Nozzle to vessel Visual (IWA- No - Note 9 welds 5000)

C: - C-C Integrally welded Surface Yes - Notes 19, supports 24, 32 l3 C' C-D "

Pressure-retaining Visual & Yes - Note 19 bolting either Sur-f ace or Volu-metric C C-A Boron Injection VIII Circumferential butt Visual (IWA- No - Note 9 Tank (1) welds 5000)

C C-B Nozzle to vessel Visual (IWA- No - Note 9 welds 5000)

C' C-C Integrally welded Visual (IWA- No - Note 9 supports 5000)

C' C-D Pressure-retaining Visual (IWA- No - Note 9 bolting 5000)

Cl C-A Accumulators (4) III C Circumferential butt Visual (IWA- No - Note 9 welds 5000)

C! . ' C-B Nozzle to vessel Visual (IWA- No - Note 9 welds 5000)

E2-4 Supplement 3 Feb. 1979

INLIAN POINT NUCLEAR GENERATING UNIT NO, 2 ^

INSERVICE INSPECTION PROGRAM - QUALITY GROUP B COMPONENTS IEJ IWC 2Cro 2500 IT.

EXAM. SYSTEM OR FAB. AREA TO BE EXAMINATION SECTION XI I: ' CAT. COMPONENT CODE EXAMINED REQUIREMENT CODE RELIEF C? i C-F, Piping Systems B31.1 Circumferential butt Volumetric Yes - Notes 26, C-G welds 27,28,31,33 l2,3 C :' - C-F, Longitudinal weld Volumetric Yes - Notes 26, C-G joints in fittings 27,28,29,31,33 l 2,3 C. C-F, " " "

Branch pipe to pipe Volumetric Yes - Notes 26, C-G weld joints 27,31,33 l 2,3 C. C-D " " "

Pressure-retaining Visual & Yes - Notes 26, bolting either Sur- 31 2,3 face or Volu-metric C. C-E-1 " " "

Integrally welded Surface Yes - Notes 26, l 2,3 supports 31,32 C C-E-2 Support components Visbal Yes - Notes 26, { 2,3 31 C C-F Residual Heat ---

Pumo casing welds N/A No - Note 3 Removal Pumps (2)

" " Yes - Notes 19, C C-D ---

Pressure-retaining Visual &

bolting either Sur- 31 2

face or Volu-metric -

C_ C-E-l ---

Integrally welded N/A No - Note 3 supports Supplement 3 E2-6 Feb. 1979

INDIAN POINT NUCLEAR GENERATING UNIT NO, 2 INSERVICE INSPECTION PROGRAM - QUALITY GROUP B COMPONENTS 11 IWC 2f 2500 It EXAM. SYSTEM OR FAB. AREA TO BE EXAMINATION SECTION XI CAT. COMPONENT CODE EXAMINED REQUIREMENT CODE RELIEF C~ C-D Safety Injection ---

Pressure-retaining Visual (IWA- No - Note 9 Pumps (3) bolting 5000 C: C-E-1 " " --- Integrally welded Visual (IWA- No - Note 9 supports 5000)

C C-E-2 ---

Support components Visual (IWA- No - Note 9 5000)

C C-G Containment Spray ---

Pump casing welds Visual (IWA- No - Note 9 Pumps (2) 5000)

CE C-D " " --- Pressure-retaining Visual (IWA- No - Note 9 bolting S000)

" " No - Note 9 C. C-E-1 ---

Integrally welded Visual (IWA-supports 5000)

C: C-E-2 ---

Support components Visual (IWA- No - Note 9 5000)

C2 C-F, Valves ---

Valve body welds N/A No - Note 3 C-G CJ C-D " ---

Pressure-retaining Visual & Yes - Notes 26, bolting either Sur- 31 2,3 e face or Volu-metric C.I . C-E-1 ---

Integrally welded N/A No - Note 3 supports E2-8 Supplement 3 Feb. 1979

INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 INSERVICE INSPECTION PROGRAM - QUALITY GROUP B COMPONENTS IK' IWC 2M' 2500 I '. EXAM. SY. STEM OR FAB. AREA TO BE EXAMINATION SECTION XI

! CAT. COMPONENT CODE EXAMINED REQUIREMENT CODE RELIEF CJ C-E-2 Valves ---

Support components Visual Yes - Notes 26,33 2,3 Supplement 3 E2-9 Feb. 1979

3]. :xception is taken to the examination area distribution requirements of IWC-2411 for the examinations required by IWC-2520. For components and piping systems in multiple

treams of similar design, size and sqrvice, the required examinations may be performed

>n one component or stream rather than distributed among the components or streams.

rhis approach will provide the equivalent degree of surveillance and is consistent with

he requirements of the Summer, 1976 addenda and subsequent Section XI editions and 2 iddenda.

3.' . Applicable construction codes required only visual examination of integral support zelds. During inservice inspection, surface examination will be employed and indica-tions previously accepted by visual examination may require further evaluation. Such indications will be evaluated in accordance with the as-constructed codes. Minor sur-

-ace indications resulting from the original welding process which are determined not no be cracks or lack of fusion and not service connected will not require further tetion. These indications will not adversely affect overall weld integrity as evi-lenced by the satisf actory performance of these welds to date.

3~. ?he piping system welds were constructed in accordance with and satisfied the require-tents of the codes and specifications applicable at the time of construction. The integrity of these welds have been further verified by satisfactory performance during

>lant operation. The original fabrication codes and specifications did not require iltrasonic examination of welds. Conditions such as high and irregular weld crowns ir rough surface finish may limit ultrasonic transducer contact to less than that

-quired to completely scan the examination volume. In such instances, examination rill be performed to the extent practical consistent with these limitations. Such

'onditions shall be identified and documented in the examination results. 3 Supplement 3 E2-13 Feb. 1979

ENCLOSURE 5 Inservice Test Program Quality Group A, B & C Pumps Indian Point Unit No. 2 August, 1977 Supplement 3 Feb. 1979

Indian Point Nuclear Generating Unit No. 2 Inservice Test Program - Quality Group A, B & C Pumps 1.0 PUMPS SUBJECT TO THE TESTING REQUIREMENTS OF SUBSECTION IWP:

Safety Inject ~ ion Pumps 21, 22 & 23 Residual Heat Removal Pumps 21 & 22 Containment Spray Pumps 21 & 22 Component Cooling Pumps 21, 22, & 23 Auxiliary Component Cooling Pumps 21 & 22 Service Water Pumps 21, 22, 23, 24, 25 & 26 Auxiliary Boiler Feedwater Pumps (Motor Driven) 21 & 23 Recirculation Pumps 21 & 22 2.0 TEST FREQUENCY DURING NORMAL PLANT OPERATION 2.1 All Pumps Except Component Cooling, Service Water and Recirculation Pumps:

The nominal pump test frequency as specified in subsection INP requires pump testing once each month during normal plant opera-tion. In a total of over 300 monthly tests completed during the last 5 1/2 years to satisfy Technical Specification requirements -

approximately 25 tests per pump - the safety injection, residual heat removal, containment spray, auxiliary component cooling and motor driven auxiliary boiler feedwater pumps have demonstrated no significant change in operating characteristics. In light of this experience, exception is taken to performing monthly tests on these pumps with an alternate proposed two-month test interval scheduled. Based on the preceding test results, the two-month l test interval will not significantly alter the operational readi-ness of these components and will decrease pump wear-out over the plant life time. The interval between successive tests shall not  ;

exceed two months ( 25%). Accordingly, during normal plant operation, each pump shall be tested at least six times per year at approximately equal intervals.

2.2 Component Cooling and Service Water Pumps:

Unlike the pumps noted in 2.1 above, these pumps operate during normal plant operation, and therefore, periodic pump testing has never been required. When modifications to provide the necessary instrumentation are completed, data collection will proceed on a monthly schedule consistent with subsection IWP. The interval between successive tests shall not exceed one month ( 251). Ac-cordingly, during normal plant operation, each pump shall be tested at least twelve times per year at approximately equal intervals.

'3 ES-1 Supplement 3 Feb. 1979

L-2.3 Recirculation Pumps The recirculation pumps are located inside containment and are not accessible for testing during normal plant operation. Consequently, exception is taken to testing these pumps at the frequency speci-fled by subsection INP. Testing of these pumps will be performed during refueling shutdowns. This is consistent with present Tech-nical Specification requirements for recirculation pump surveil-lance testing.

3.0 TEFT FREQUENCY DURING AND FOLLOWING SHUTDOWNS 3.1 All Pumps Except Safety Injection, Motor Driven Auxiliary Boiler Feedwater and Recirculation Pumps:

Consistent with paragraph IWP-34 00 (a) , the pump test schedule shall not be maintained during shutdown periods. Accordingly, when not tested during shutdowns, the residual heat removal, c or.-

tainment spray, component cooling, auxiliary component cooling and service water pumps shall be tested prior to attaining criticality, when returning the plant to service.

3.2 Safety Injection and Motor Driven Auxiliary Boiler Feedwater Pumps:

~

Present plant Technical Specifications and related commitments require full flow testing of the safety injection and motor driven auxiliary boiler feedwater pumps prior to start-up follow-ing each reactor refueling. These full flow tests differ from the Section XI required tests of these pumps which are performed under minimum flow conditions using recirculation loops. Full flow tests are maximum capability tests and serve to verify pump operability at conditions closely approximating those for which the pumps are designed. It is intended that these full flow tests serve in lieu of the Section XI required recirculation flow tests during refueling shutdowns. Subsequent recirculation flow tests will commence.two months ( 25%) from the corresponding full flow test. Although flow rate, suction, discharge and differen-tial pressures will be obtained during full flow testing, test results will'nct be comparable to those obtained from recircula-tion tests. Exception is therefore taken to obtaining Section XI specified test data during full flow tests for purposes of com-parison with those obtained during recirculation flow tests.

3.3 Recirculation Pumps:

As noted in paragraph 2.3 above, the recirculation pumps are not accessible for testing during normal reactor operation. Testing will be performed during reactor shutdowns for refueling.

3 E5-2 Supplement 3 Feb. 1979

4.0 INSERVICE PUMP TEST PROGRAM TABULATION The following tabulation lists each of the pump parameters to be measured or observed and the test interval for recording of those parameters. Justification for exceptions to the Section XI rules (with the exception of test frequency which is discussed in para-graphs 2.0 and 3.0 above) are provided in the notes following the tabulation. 3 ES-3 Supplement 3 Feb. 1979

INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 INSERVICE TEST PROGRAM QUALITY GROUP A, B AND C PUMPS PUMP QUALITY PARAMETERS TEST lhosSNI.!br

'.NTIFICATION GROUP MEASURED / OBSERVED INTERVAL  :(except test g frequency) 3 S. :ty Injection B 1. Speed (if variable) N/A N/A Pt . :s 21, 22 and 2. Inlet Pressure (Pi) Two Months Yes - Note 1 2- 3. Outlet Pressure (Po) Two Months Yes - Note 1

4. Differential Pressure (Po-Pi) Two Months Yes Yes Note Note 1

1

5. Flow Rate (Q) Two Months

6. Vibration Amplitude (V) Two Months No

7. Lubricant Level or Pressure Two Months No

8. Bearing Temperature (Tb) Yearly Yes - Note 5 3 E . dual Heat B 1. Speed (if variable) N/A N/A F . val Pumps 2. Inl'et Pressure (Pi) Two Months No

.' :nd 22 3. Outlet Pressure (Po) Two Months No

4. Differential Pressure (Po-Pi) Two Months No - Note 7

5. Flow Rate (Q) Two Months No

6. Vibration Amplitude (V) Two Months No

7. Lubricant Level or Pressure N/A No - Note 8 l

8. Bearing Temperature (Tb) Yearly Yes - Note 5 L3

( ainment Spray B 1. Speed (if variable) N/A N/A 1 s 21 and 22 2. Inlet Pressure (Pi) Two Months No

3. Outlet Pressure (Po) _Two Months No

4. Differential Pressure (Po-Pi) Two Months No - Note 7

5. Flow Rate (Q) Two Months No

6. Vibration Amplitude (V) Two Months No

7. Lubricant Level or Pressure Two Months No

8. Bearing Temoerature (Tb) Yearly Yes - Note 5 3 C onent Cooling C 1. Speed (if variable) N/A N/A P is 21, 22 and 2. Inlet Pressure (Pi) N/A Yes - Note 2

c. 3. Outlet Pressure (Po) N/A Yes - Note 2

4. Differential Pressure (Po -Pi) N/A Yes - Note 2

5. Flow Rate (Q) N/A Yes - Note 2

6. Vibration Amplitude (V) N/A Yes - Note 2

7. Lubricant Level or Pressure N/A Yes - Note 2 [3

8. Bearing Temperature <Tb) N/A Yes - Note 2 E5-4 Supplement 3 Feb. 1979

INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 INSERVICE TEST PROGRAM QUALITY GROUP A, B AND C PUMPS PUMP QUALITY PARAMETERS TEST loShkNLIhr

.NTIFICATION GROUP INTERVAL (except test g J MEASURED / OBSERVED . frequency) a3 At liary Compo- C 1. Speed (if variable) N/A N/A

r. -

Cooling 2. Inlet Pressure (Pi) Two Months No - Note 4 P' s 21 and 22 3. Outlet Pressure (Po) Two Months No - Note 4

4. Differential Pressure (Po-Pi) Two Months No - Note 4 No

5. Flow Rate (Q) Two Months

6. Vibration Amplitude (V) Two Months No

7. Lubricant Level or Pressure N/A No - Note 8

8. Bearing Temperature (Tb) Yearly Yes - Note 5 3 E ice Water C 1. Speed (if variable) N/A N/A l' s 21,22, 23, 2. I n 1'e t Pressure (Pi) N/A Yes - Note 3 2 25 and 26 3. Outlet Pressure (Po) N/A Yes - Note 3

4. Differential Pressure (Po-Pi) N/A Yes - Note 3

5. Flow Rate (Q) N/A Yes - Note 3

6. Vibration Amplitude (V) N/A Yes - Note 3

7. Lubricant Level or Pressure N/A Yes - No te 8 3

8. Bearing Temperature (Tb) N/A Yes - Note 3 I liary Feed- C 1. Speed (if variable) N/A N/A

t. r Pumps 21 2. Inlet Pressure (Pi) Two Months No c 23 3. Outlet Pressure (Po) Two Months No t or Driven) 4. Differential Pressure (Po-Pi) Two Months No - Note 6 3

5. Flow Rate (Q) N/A No - Note 4

6. Vibration Amplitude (V) Two Months No

7. Lubricant Level or Pressure Two Months No

8. Bearing Temperature (Tb) Yearly Yes - Note 5 3 1 rculation B 1. Speed (if variable) N/A N/A I s 21 and 22 2. Inlet Pressure (Pi) Eefuelings No *

3. Outlet Pressure (Po) '

Refuelings No

4. Differential Pressure (P o-Pi, Refuelings Yes - Note 7 3

5. Flow Rate (Q) N/A No - Note 4-

6. Vibration Amplitude (V) Refuelings No

7. Lubricant Level or Pressure N/A No - Note 8 3

8. Bearing Temperature (Tb) Refuelings Yes - Note 5 E5-5 Supplement 3 Feb. 1979

NOTES - INSERVICE TEST PROGRAM Ouality Group A, B and C Pumps

1. Functional requirements for the safety injection pumps, based on the most recent ECCS analysis and as currently specified in the safety injection pump functional test pro-cedure, are as follows:

CRITERIA A (Miniflow Conditions of 25 to 35 gpm) -

(a) the safety injection pumps shall be considered operable if the pump heads are greater than 3,292 feet or, (b) if one pump head is bel.ow 3,292 feet, the safety injection pumps shall be t ..-

sidered operable if~the heads for the two higher head pumps are in the acceptance region of attached Figure E5-1.

CRITERIA B (Miniflow Conditions of less than 25 opm for one or more pumps) -

(a) the safety injection pumps shall be considered operable if the pump heads are greater than 3,311 feet, or (b) if one pump head is below 3,311 feet, the safety injection pumps shall be consid-ered operable if the heads for the two higher head pumps are in the acceptance region of attached Figure E5-2.

3 Exception is taken from having to meet the allowable ranges of test quantities as defined in Table IWP-3100-2 for the safety injection pump hydraulic performance pacameters, with substitution of the currently defined parameters as permitted under IWP-3210.

. Due to the demands of dependent systems, the individual testing of component cooling pumps as required by IWP-3400 (a) could jeopardize plant operation. Although instru-mentation is installed which will permit the recording of inlet pressure of each pump, pressure measurement on the pump discharge can only be monitored at the common discharge header. The plant design does not incorporate independent flow measure- [

ment instrumentation. Currently, correct performance of these pumps can only be assessed on their continued ability to perform their intended function. An Engineer- (

ing review is underway to provide for independent measurement of the hydraulic param-eters for each pump as required by IWP-3 4 00 (a) and exception is taken to implementing the required tests on these pumps until modifications have been completed.

E5-6 Supplement 3 Feb. 1979

. The service water pumps are vertical design with no means of direct inlet pressure measurement as required by IWP-4200 at this time. Due to d2mands of dependent sys-tems, the individual testing of service water pumps, as required by IWP-3 400 (a) ,

could jeopardize plant operation. Although individual pump discharge pressures can be measured, the plant design does not incorporate any flow measurement instrumen-

.tation. Currently, correct performance of these pumps can only be assessed on their continued ability to perform their intended function. An Engineering review is under-way to provide for independent measurement of the hydraulic parameters of each pump and exception is taken to implementing the required tests on the service water pumps until appropriate modifications have been completed.

4. The test circuits employed for testing of these pumps are considered as fixed resis-tance systems. In accordance with Table IWP-3100-1, either differential pressure or flow rate require measurement, not both.

5. Exception is taken to the time in' orval requirements between successive measurements of bearing temperature as specified by paragraph IWP-3500(b). Pump operating time for purposes of testing is severely limited by potential pump overheating under the min imum flow conditions dictated by the test circuit. Accordingly, bearing tempera-tu: 2 will be measured once, after fifteen minutes of pump operation as experience indicates bearing temperature to be sufficiently stabilized at that point.

Co sistent with paragraph INP-3210, alternate range limits of 1350 to 1550 psi are substituted for the acceptable range of differential pressure in lieu of the accept-able range specified in Table IWP-3100-2.

The manufacturer's certified head-flow curve, established by test prior to pump in-stallation, shall serve as the reference quantities for head and flow. The pump shall be considered acceptable for service (acceptable range of Table INP-3100-2) if in subsequent tests, developed head does not decrease by more than 5% of the manufacturer's certified head on recirculation flow. This 5% derating is consistent with the ECCS analysis which takes into account the effects of normal pump wear on pump performance over the life of the plant. It should be noted that the Section XI specified upper limits for head are of little practical value when using the manufac-turer's certified head-flow curve as the reference quantity since under normal test conditions the manufacturer's quantities cannot be exceeded. Data exceeding the manufacturer's quantities are indicative of non-standard test conditions attributable to varied system alignments or other test prerequisites.

L. The design of these pumps does not incorporate independent lubrication systems having measurable or observable charact eristics. Lubrication is either by sealed grease type bearings or pumped fluid.

3 E5-7 Supplement 3 Feb. 1979

Figure E5 SAFETY INJECTIO!! PUMP ACCEPTA!!CE CRITF7P!IA A

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ENCLOSURE 6 Inservice Test Program Quality Group A, B& C Valves Indian Point Unit No. 2 September, 1977 (Supplement 1) d up, lc:. c:i t. 3 Feb. 1979

Indian Point Nuclear Generating Unit No. 2 Inservice Test Program - Quality Group A, B & C Valves

1.0 GENERAL

This valve inservice test program addresses the requirements for Quality Group A, B and C valves. Those valves which are used for operating convenience only, such as manual vent, drain, instru-ment and test valves, and valves used for maintenance only are excluded from the inservice test program per IWV-1300.

2.0 VALVE STROKE TIME MEASUREMENT:

Paragraph INV-3 410 (c) of the ASME Code Section XI requires that the stroke time of all power-operated Category A and B valves be measured during the performance of their required exercising tests.

Motor operated valves (which have various specified maximum stroke times depending on system and application) are the only valves considered to be " power-operated" within the context of this re-quirement and, accordingly, will be tested for stroke time as required. In addition, although air-operated valves are not required to be tested for stroke time, certain air-operated valves will have their stroke times measured where special timing re-quirements have been specified and established in order to prevent or mitigate the consequences of a postulated accident.

3.O VALVE TESTING FREQUENCY DURING NORMAL OPERATIONS :

As required by INV-3000, valves are full-stroke exercised during normal plant operation where practical. For Category A and B valves which can be exercised "on-line", the testing interval between successive tests shall not exceed 3 months ( 25%). The allowed 25% extension to a testing interval is consistent with current NRC surveillance testing philosophy. Furthermore, the overall intent of the Section XI INV-3400 requirements is met in that each "on-line" valve will be tested at least 4 times per year at approximately equal intervals. There are no Category C valves which can be tested "on-line". Category D and E valves do not re-quire any "on-line" testing. The "on-line" testing shall be suspended during the performance of the "off-line" testing de-scribed in Section 4. 0 below.

4.0 VALVE TESTING FREQUENCY DURING AND FOLLOWING SHUTDOWNS:

During the development of this valve testing program, those valves which cannot be full-stroke exercised "on-line" were determined. These valves were identified as such since their operation would either jeopardize the integrity of their systems or would cause perturbations within their systems suf ficient to rncnit in n n ] ,, n

• u-4m. rn- ukn c,-n -n,c--c, r,r*_cu vn t- n .

E6-1 Supplement 3 Feb. 1979

exercising of these valves "on-line" was also determined to be impractical. Accordingly, these "off-line" valves shall be full-stroke tested when the plant is in the cold shutdown condition.

IWV-3000 requires that valves which cannot be operated during nor-mal plant operation be full-stroke exercised at each cold shutdown.

In case of frequent cold shutdowns, the requirements state that such Category A and B valves need not be exercised more often than once every 3 months and that Category C check valves need not be exercised more often than once every 9 months. Exception is taken to these requirements. More than half of the Category A and B valves and Category C check valves (i.e., approximately 54%) included in the valve inservice test program cannot be operated during normal plant operation and can only be exercised during a cold shutdown period. Because of the considerable time and manpower required to perform the complete exercising test for such a large and varied group of valves, all "off-line" valves will be tested only at cold shutdown during refueling outages.

Cold shutdown outages, whether scheduled or unscheduled, which occur between refuelings do not provide sufficient time to per-form such testing and the diversion of needed manpower unduly extends the outage. Refueling outages are of sufficient dura-tion such that the "off-line" valve testing program can be con-ducted with minimal impact on outage critical path. Accordingly, valves that cannot be full-stroke exercised during normal plant operation shall be full-stroke exercised at cold shutdown during refueling outages.

5.0 INSERVICE VALVE TEST PROGRAMS - DETAILED DESCRIPTION:

The following pages contain the detailed description of the inser-vice valve test program. The Quality Group A, B and C valves have been categorized as required by the Section XI Code into Cate-gory A, B, C, D and E valves. The valve testing program will be conducted as described in the following pages and exceptions to the Section XI rules (with the exception of test frequency which is discussed in paragraphs 3.0 and 4.0 above) are addressed for each category where applicable. 3 E6-2 Supplement 3 Feb. 1979

CATEGORY A VALVES The Category A valves identified below are containment isolation valves and will be leak tested at a frequency of not less than once every two years as required by Appendix J to 10CFR50 and as specified in the technical specifications. The performance of the Appendix J Type C containment isolation valve leak rate testing shall be considered to satisfy the requirements of IWV-3420 for Category A valves. 3 The Category A valves identified below will also be full-stroke exer- l cised at 3 month intervals during normal plant operation, as required by IWV-3410, with the exception of those valves marked (1), (2), (3),

j3 (4), (5) or (6). The exceptions or code relief represented by these notes are as follows:

(1) These valves cannot be operated during normal plant operation and will be full-stroke exercised only during cold shutdown at refuel-ing outages. As discussed earlier, no part-stroke exercising during normal plant operation has been deemed practical for any 3 of these valves.

(2) These valves are either locked open or locked closed manual con-tainment isolation. valves and as such are categorized as Category

. AE valves. As a result of their locked status, these valves will satisfy the Category E requirements set forth in INV-3700. How-ever, since they are containment isolation valves, these valves will also satisfy the Category A leak testing requirements of IWV-3420 but will be exempt from the exercising requirements of IWV-3410.

(3) These valves are check valves that serve as containment isolation valves and as such are c.ategorized as Category AC. Accordingly, these valves will satisfy the Category A leak testing require-ments of IWV-3420. Existing plant design and construction pro-vides no means for indication or verification of check valve disk motion in either direction. However, proper position for satisfying the containment isolation function is confirmed by acceptable Category A valve leak rate testing results. Therefore, these Category AC check valves will be exempt from the exercising requirements of IWV-3410 and IWV-3520.

(4) These valves are containment isolation valves for instrument lines used only for testing. Such a line is normally excluded from IWV testing requirements per IWV-1300. However, since these valves perform a containment isolation function, they will satisfy the requirements of IWV-3420 but will be exempt from the requirements of IWV-3410.

(5) These valves are relief valves that also serve as containment iso-lation valves. Therefore, they are categorized as Category AC. As E6-3 Suppl.cment 3 Feb. 1979

a result, they will satisfy the Category A leak testing require-ments of IWV-3420. They will, however, be exempt from IWV-3410 exercising requirements since as relief valves they will satisfy the requirements of IWV-3510.

(6) These valves are used for maintenance purposes only but also con-stitute the containment isolation boundary for their particular lines. Since this type of maintenance valve is normally excluded from IWV testing per IWV-1300, these valves will satisfy the re-quirements of IWV-3420 but will be exempt from the exercising requirements of IWV-3410.

Safety Injection System 867B (3) 867A (3) 888A E 3 869B (2) 869A (2) 888B 878A (2) 850B (2) 850A (2) 863 878B (2) 851B 851A 4312 (3) 743 (2) 859A (2) 885A 1870 (2) 859C (2) 885B 3_

Auxiliary Coolant System Chemical Volume & Control System 744 (1) 793 222 (1) 250A (1) 741 (3) 798 226 (1) 241B (1) 732 (2) 791 227 (1) 250B (1) 797 (1) 205 (1) 241C (1) 784 (1) 201 (1) 250C (1)

FCV-625 (1) 202 (1) 241D (1) 796 241A (1) 250D (1)

Reactor Coolant System Sampling System 549 580A (4) .956A 956H 548 5808 (4) 956B 958 550 956C 959 518 (3) 956D 990C 552 956E 990A 519 956F 990B 956G Post Accident Containment Air Sampling System Service Water System 18~/5A 1875G SWN-41 (5 valves) (1) 1875B 1875H SWN-42 (5 valves) (5) 1875C 1875J SWN-43 (5 valves) (6) 1875D SWN-44 (5 valves) (1) 1875E SWN-51 (5 valves) 1875F SWN-71 (5 valves) (1)

E6-4 Supplement 3 Feb. 1979

Steam Generator Blowdown &

Hydrogen Recombiner System Sampling System 1882A 4430 PCV-1223 PCV-1214 1882-9 (4) IV-5A PCV-1223A PCV-1214A 4432 1876-8 (4) PCV-1224 PCV-1215 IV-5B '4429 PCV-1224A PCV-1215A 1876-9 (4) IV-3A PCV-1225 PCV-1216 4431 1875-8 (4) PCV-1225A PCV-1216A 3 IV-3B IV-2A PCV-1226 PCV-1217 1875-9 (4) IV-2B PCV-1226A PCV-1217A Waste Disposal System 1786 1789 1787 1702 1610 1705 1616 (3) 1728 1788 1723 Miscellaneous Containment Isolation Valves 1234 - Containment Air Sample 1235 - Containment Air Sample 1236 - Containment Air Sample 1237 - Containment Air Sample PCV-1229 - Air Ejector to Containment PCV-1230 - Air Ejector to Containment SA-24 (2 valves) (6) - Service Air To Containment UH-43 (2) - Auxiliary Steam System UH-44 (2) - Auxiliary Steam System 1170 (1) - Containment Purge System 1171 (1) - Containment Purge System 1172 (1) - Containment Purge System 1173' (1) - Containment Purge System 1190 (1) - Containment Pressure Relief System 1191 (1) - Containment Pressure Relief System 1192 (1) - Containment Pressure Relief System IA-39 (3) - Instrument Air / Post-Accident Venting Supply PCV-1228 (1) - Instrument Air / Post-Accident Venting Supply E-1 - Post-Accident Venting Exhaust E-2 - Post-Accident Venting Exhaust E-3 - Post-Accident Venting Exhaust E-5 - Post-Accident Venting Exhaust MW-17 (2 valves) (6) - City Water to Containment 1814A (2) - Containment Pressure Sensing Instrument Lines 1814B (2) - Containment Pressure Sensing Instrument Lines 1814C (2) - Containment Pressure Sensing Instrument Lines 85A (3) - 80'-el Personnel Airlock 85B (3) - 80'-el Personnel Airlock 85C (1) - 80'-el Personnel Airlock 73 (1) . -o '. - '

E6-5 Supplement 3 Feb. 1979

Miscellaneous Containment Isolation Valves (cont'd) 95A (3) - 95'-el Personnel Airlock 95B (3) - 95'-el Personnel Airlock 95C (1) - 95'-el Personnel Airlock 95D (1) - 95'-el Personnel Airlock E6-6 Supplement 3 Feb. 1979

CATEGORY B VALVES .

The Category B valves identified below are those Quality Group A, B and C valves that may be required to change position for fulfillment of their functions following an accident or for safe shutdown and, there-fore, are required to be exercised to the required position by IWV-3410.

,These valves will'be full-stroke exercised at 3 month intervals during E 3

normal operation with the exception of those valves marked (1) or (2).

The exceptions or code relief represented by these notes are as follows:

(1) These valves cannot be operated during normal plant operation and will be full-stroke exercised only during cold shutdown at refuel-ing outages. As discussed earlier, no part-stroke exercising dur-ing plant operation has been deemed . practical for any of these valves. 3 (2) These valves are the main steam isolation valves (MSIVs) and are categorized as Category BC. They are stop-check type valves with pneumatic operators holding the valve disks out of the main steam flow path. The MSIVs will satisfy the exercising requirements of IWV-3410 but, as permitted by INV-3410 (b) (1) , will be full-stroke exercised only during cold shutdown at refueling outages as presently required by the plant technical specifications. Part- 3

- stroke exercising of these valves during normal plant operation is not practical.

Safety Injection System 866C 887A 1822A 880C 866D 887B 1822B 880D 856C (1) 889A 1821 880E 3 856D (1) 889B 1802A 880F 856F (1) 882 (1) 1802B 880G 866A 842 (1) 894D (1) 880H 866B 843 (1) 894A (1) 880J 856A (1) 876A 894B (1) 880K 856E (1) 876B 894C (1) 898 856B (1) 1810 (1) 880A 891A 1805 1831 880B 891B 891C 891D 3 Auxiliary Coolant System 745A RCV-017 747 756B (1) 745B 822B (1) 756A (1) 1873C 730 (1) 734B 734E 1873D 731 (1) HCV-638 734F 831

__ 822A (1) HCV-640 1873A 733C 4

734A 746 1873B '

T6u (1) "3 E6-7 Supplenent 3 Feb. 1979

Chemical Volume & Control System 1100 LCV-459 (1) TCV-14 9 (1) 364 (1) 1247 204A (1) 309 (1) 367A 1133 204B (1) 311A (1) 367B PCV-1049 (1) 213 (1) 340A (1) HCV-105 1269 HCV-123 (1) 346 (1) 366 (1) 1679 215 (1) 352 (1) HCV-104 1109 PCV-135 (1) 269 (1) 358 1104 271 (1) FCV-lllB (1) 372 1119 310 (1) LCV-112C (1) 295 53 1120 313 (1) FCV-110B (1) 285 200A (1) LCV-ll2A (1) 293 (1) FCV-lllA (1) 200B (1) 387 (1) FCV-110A (1) 265 200C (1) 391 (1) LCV-ll2B (1) 268 HCV-133 (1) 343B (1) 288 (1) 212 (1) 323B (1) 333 (1)

Reactor Coolant System Sampling System PCV-455B (1) PCV-455C (1) 951 974A PCV-455A (1) 953 974B 536 (1) 955A 975 PCV-456 (1) 955B 535 (1)

Main Steam System Condensate & Boiler Feedpump System PCV-ll35 PCV-ll37 LCV-ll58 PCV-ll87 MS-1.22 (2) MS-1-24 (2) PCV-1188 PCV-ll89 PCV-1134 MS-41 MS-1-21 (2) MS-42 PCV-ll36 PCV-1310 A (1)

MS-1-23 (2) PCV-1310B (1) 3 PCV-ll39 HCV-lll8 Boiler Feedwater System FCV-427 (1) FCV-437L (1) FCV-406D FCV-ll21 FCV-427L (1) FCV-417 (1) FCV-405C PCV-1213 FCV-447 (1) FCV-417L (1) FCV-405A BFD-74 FCV-447L (1) FCV-406B FCV-405B FCV-437 (1) FCV-406A FCV-405D FCV-406C FCV-ll23 (1) [3 Service Water System SWN-31 (1) SWN-29 FCV-lll2 (1)

SWN-33 (2 valves) (1) FCV-llll (1) TCV-1104 SWN-38 (1) TCV-1105 FCV-ll76A SWN-40 (2. valves) (1) FCV-ll76 SWN-32 (1)

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SWN-7 (1) SWN-30 (1) 3 E6-8 Supplement 3

CATEGORY C VALVES

. Check Valves:

INV-3520 requires periodic exercising of Category C check valves. With the exception of a number of engineered safeguards valves in the Safety Injection, Main Steam, and Containment Isolation Systems, existing plant design and construction provides no means for testing check valves nor any means for indication or verification of check valve disk posi-tion. However, proper operation of Quality Group A, B and C systems and absence of any indicated or observable abnormalities assures proper operation of check valves within these systems. Accordingly, except for those check valves discussed below, exception is taken to satisfy- 3 ing the exercising requirements of INV-3520.

Those check. valves that serve as containment isolation valves are cate-gorized as Category AC and are identified in the " Category A Valves" listing by note (3). These check valves will'be tested as described therein.

Those stop-check type valves that serve as the Main Steam Isolation Valves (MSIVs) are categorized as Category BC and are identified in the " Category B valves" listing by r.ote (2). These MSIVs will be tested as described therein.

The Category C check valves identified below are located in the Safety Injection System and are tested during cold shutdown at refueling in-

ervals for flow by system operation and for gross reverse leakage (i.e. closure) by means of system draining and use of installed test connections. These valves represent the reactor coolant system pressure boundary for their particular lines and as such prevent everpressurizing the Safety Injection System during normal operation. The above opera-bility tests satisfy the exercising requirements of IWV-3520 but excep-tion is taken to the testing frequency. Because of the substantial effort involved in the testing, these valves will be tested at refueling in-tervals.

Safety Injection System 857A 857G 895A 897C 857B 857H 895B 897D 857C 857J 895C 838A 857D 857K 895D 838B 857E 857L 897A 838C 857F 857M 897B 838D II. Safety / Relief Valves:

IWV-3510 requires periodic testing of safety and relief valves. The Category C safety / relief valves identified below will be tested in accordance with IWV-3510 at the frequency defined in Table INV-3510-1 except as noted. Those relief valves that--provide a containment isola- 33

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E6-9 Supplement 3 Feb. 1979

(1). These particular relief valves will satisfy the Category A leak

,est requirements of IWV-3420 but will be exempt from IWV-3410 exer-cising requirements since as relief valves they will satisfy IWV-3510.

Those valves marked below as (2) and (3) are the pressurizer safety valves and main steam safety valves, respectively. The unit technical specifications presently require testing for these valves at refueling intervals which is more conservative than applying the test frequency established by Table IWV-3510-1. These 23 valves (pressurizer and main steam safety valves) shall continue to be tested at refueling intervals and the remaining relief valves, which are subject to the testing requirements of IWV-3510, shall be tested at a frequency consistent with Table INV-3510-1. The testing of the 23 valves de-scribed above shall not be considered for satisfying the requirements of Table INV-3510.

Auxiliary Coolant System relief valves 819A and 819B (marked as (4) below) shall be exempt from the testing requirements of INV-3510.

These valves are located on the component cooling water return line from the residual heat removal heat exchangers. Their locations (in-side containment) are inaccessible during normal operation. In addi-tion, the system must be operating when the unit is in the cold shut-down condition to remove decay heat from the reactor core. Furthermore, these valves are welded in place and have no means provided for isola-tion from the system for testing. Finally, these valves are located in a very high radiation area and simple access to the valves results

.n significant personnel radiation exposure. Accordingly, because of plant design, the above stated reasons demonstrate the impracticality of testing relief valves 819A and 819B and they shall be exempt from INV-3510 testing requirements. 3 E6-10 Supplement 3 Feb. 1979

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_ Safety Injection System Auxiliary Coolant System 855 892D 782 1836 1828 783A 819A (4) 3 3 1815 783B 835 892A 783C 819B (4) E

~3 892B 783D 785B 892C 792 Chemical Volume & Control System Reactor Coolant System 218 231 PCV-464 (2) 203 234 PCV-466 (2) 263 237 PCV-468 (2) 3 264 Condensate and Boiler Feedpump Main Steam System System CT-35 (3 valves) MS-45 (4 valves) (3)

MS-46 (4 valves) (3)

MS-47 (4 valves) (3)

MS-48 (4 valves) (3)

_ MS-49 (4 valves) (3) 3 MS-52 Service Water System Boiler Feedwater System SWN-42 (5 valves) (1) BFD-69 SWN-63 (3 valves)

SWN-36 (2 valves)

E6-ll Supplement 3 Feb. 1979

CATEGORY D VALVES Ihere are no Category D valves at Indian Point Unit No. 2.

CATEGORY E VALVES The Category E valves identified below will satisfy the requirements of IWV-3700. That is, operational checks, with appropriate record entries, will record the position of these valves before operations are performed and after operations are completed, and verify that each valve is locked or sealed in its required position.

Those normally locked valves that also perform a containment isolation function are categorized as Category AE and are marked (1) below.

These valves will satisfy the IWV-3420 leak testing requirements but, since they are locked in position, will satisfy IWV-3700 requirements and will be exempted from IWV-3410 exercising requirements as described in note (2) of the " Category A Valves" listing.

Safety Injection Systen 869B (1) 850A (1) 1806A 743 (1) 850B (1) 846 1806B 1870 (1)

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859A (1) 878A (1) 1841 1823F 859C (1) 878B (1) 1839A 873B 869A (1) 1860 1839B Auxiliary Coolant System Chemical Volume & Control System 739A 735A 281 371 739B 1819 273 1263 742 735B 276 1264 732 (1) 832 359 1102 Boiler Feedwater System Auxiliary Steam System BFD-51 BFD-78 UH-43 (1)

BFD-77 UH-44 (1)

Containment Pressure Sensing Instrument Lines 1814A (1) 1814B (1) 1814C (1) e E6-12 Supplement 3 Feb. 1979