ML19031A660

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02/28/1977 Letter Inservice Inspection and Testing Programs
ML19031A660
Person / Time
Site: Salem  PSEG icon.png
Issue date: 02/28/1977
From: Librizzi F
Public Service Electric & Gas Co
To: Kniel K
Office of Nuclear Reactor Regulation
References
Download: ML19031A660 (38)
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Public Service Ele_ trf?).~'crGa;c~m~~

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Newark, N.J. 07101 Phone 201 /622-7000

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February 28, 1977 O~_ u. s. NUCI tAP.

1 co':1"' r<<~ig~lATORY t- S Mail Sei~~'(:

Director of -r-a~~@ or R~gu~ation U. S. Nuclear ~cy..u.~-a~Y Comm1ss1on Washington, D. C. 20555 Attention: Mr. Karl Kniel, Chief Light Water Reactors Branch 2 Gentlemen:

INSERVICE INSPECTION AND TESTING PROGRAMS NO. 1 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 Public Service Electric and Gas Company hereby transmits its Inservice Inspection, Pump and Valve Testing Programs (En-closures 1, 2~ and 3, respectively) for Unit 1 of the Salem Nuclear Generating Station.. This information is provid~d in accordance with 10CFR50.55a and your letter of request dated December 17, 19~6. The information provided in this trans-mittal supersedes that contained in our transmittal of January 14, 1977. includes requests for relief from those ASME Code Section XI Inservice Inspection Requirements that we have determined to be impractical for the Salem facility, and the inservice inspection boundary diagrams. Several of the boundary diagrams have not yet been completed. It is expected that these will be completed and transmitted to you by March 21, 1977.

As discussed in Enclosure 2, we are currrently investigating a method of measuring flow rates for those pumps that are not presently equipped with the necessary instrumentation to do so. contains a section that identifies several "special" valves that do not fit into any specific category as defined in Subsection IWV of the Code. We believe these valves should be subject to certain surveillance requirements and have described the methods we will employ to assure their operational readiness.

With regard to the Service Water System, we have reevaluated our surveillance capabilities and believe that, subject to incorpora-tion of the flow measuring equipment discussed in Enclosure 2, we can fully satisfy the Inservice Testing Requirem~nts set forth /

in the Code. .>

0 The Energy People 1-0 95-2001 (400M) 6-76

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Mr. Karl Kniel, Chief 2-28-77 Should you have any questions regarding this transmittal, do not hesitate to contact us.

Very truly yours,

-fp/*, *.

F. P. Li~

General Manager - Electric Production Production Department EAL:mlr Enclosures 6Fl 02-03

' ENCLOSURE 1

\.

ISI PROGRAM UNIT 1 SALEM GENERATING STATION Introduction The inservice inspection program of the Class 1, 2 and 3 components for the first inspection period of the first inspection interval is based on ASME Section XI, 1974 Edition, with Addenda through Summer 1975 and the Salem Nuclear Generating Station Unit 1 Technical Specifications. The Technical Specification augmentsSection XI requirements by requiring examinations of the reactor coolant pump flywheels, steam generator tubing, and additional examinations of the steam generator cladding. Exceptions to the Code are listed in Attachment 1. The program is for a period starting with date of commercial operation and continuing for 40 months following.

Repairs within the pressure-retaining boundary on components will be made in accordance to division 1 of Section XI~ or, if the particular repairs are not specified in division 1, repairs will be performed in accordance with the provisions of the Code applicable to the construction of the component.

Scope

  • Class 1, 2 and 3 components and the methods of examination for each component are listed in Tables 1, 2 and .3 respectively. The flow diagrams in Attachment 2 identify the boundaries for the Class 1, 2 and 3 components. Specific components to be examined in each class will be identified by title and/or number in the Long-Term Examination Plan.

--- Inspection Intervals The inspection interval for Class 1, 2 and 3 components and reactor coolant pump flywheels shall be 10 years. The inspection interval

  • for the steam generator tubing shall be 24 months. The inspection interval for all examinations shall start at the date of commercial operation. The Long-Term Examination Plan shall describe the distribution of examinations within the interval. The distribution shall be made in accordance with paragraph IWB-2400, IWC-2400 (see Attachment 1 for exceptions) , and IWD-2400 of ASME Section XI for Class 1, 2 and 3 components, respectively and in accordance with the.technical specificationsc The pressure test and visual examinations required by IWC-2412(a) will be performed at pressure and distribution required by IWD-2400. The distribution of examinations for the steam generator tubing and cladding and for the reactor coolant pump flywheels shall be in accordance with the technical specifications.

NOTE: Design pressure (PD) as referred to in the Code is defined as the system pressure for which over-pressure protection is provided.

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Exwnlnntion Catcr.ory 1'Allt.l~ 1 CLJ\SS l COMl'ONJ*:N'l'cl, \'i\li'l':l ,~.Nil l*U*:TIJIHJ:) Ol" EXAMltlA'l'ION **

Item 'l'nble No. HID-2500 Component~ nnd Pnrtu to be Examined Met ho cl Reactor Vessel Bl.l B-A Longitudlnnl and circumferential shell velds in core region Volumetric Bl.2 B-B Longitudi11al and circumferential velds in s\1cll (other thnn Volumetric those of Cnte1'ory B-A nnd B-C) nnu meridlonul.and circwuferential ncum V<'ld~ in bottom heud und closure head (other thun those ol' Category D-C)

Bl.3 B-C Vessel-to-flange und heud-to-l'lnnge circwnferential velds Volumetric Bl.Ii B-D Primary nozzle-to-vessel velds ar.d nozzle inside radiused Volumetric section Bl.5 B-E Vessel penetrations, including control rod drive and instru- Visual (IWA-5000) mentation penetrations Bl.6 B-F Nozzle-to-safe end velds Volumetric and Surface Bl.7 B-G-1 Closure studs, in place Volumetric Bl.8 B-G-1 Closure studs and nu~s, vhen removed Volumetric end Surface Bl.9 B-G-1 Ligll!llents betveen threaded stud holes Volumetric Bl..10 B-G-1 Closure vashers, bushings Visual Bl.13 B-I-1 Closure Head Cladding 1) Visual and* Surface, or

2) Volumetric Bl.lli B-I-1 Vessel Cladding Viaual Bl.15 B-N-1 Vessel Interior Visual Bl.16 B-N-2 Interior attachn:ents and core support structures Visual Bl.17 B-N-3 Core-support structures Visual ,

Bl.18 B-0 Control rod drive housings Volumetric Bl.19 B-P Exempted components .Visual (IWA-5000)

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Pressurizer B2.l B-B Longitudinal and circumferential velds Volumetric B2.2 B-D Nozzle-to-ves~el radi~sed section Volumetric B2.3 B-E Heater penetrations Yisua.l* (IWA-5000)

. l32.li B-F NozZle-to-safe end velds . Volumetric ru1u l:urf:>cc

d:c!.9 B-I-2 Vessel cladding VisunJ.

ll2.10 B-P Excr.ifjteu.. CO:t!10n~n*~s Vi:;u"l.l (r. *~-5"~""}

B2.ll ll-G-2 Pre3~urc-rctaininc boltinG Visual Steam Generators

!3.1 B-B Longitudinal and circumferential velds, including tube sheet.- Volumetric to-head or shell velds on the primary side

!3.2 B-D Nozzle-to-head velds end nozzle inside radiused section on Volumetric the primary side B3.3 B-F Nozzle-to-3afe end velds Volumetric and Surface

!3.8 B-I-2 Vessel Cladding Visual B3.9 - B-P Exempted components Visual (IWA-5000)

B3.10 B-G-2 Pressure-retaining bolting Visual l'ubing Eddy Current Vessel Cladding (Steam Generator Nl4) * *vol."Umetric.

Piping Pressure Boundary Bli.1 B-F Sate-end to piping velds and safe-end in brance piping velds Volumetric and Surface Bli.5 B-J Circumferential and longitudinal pipe velds Volumetric Bli.6 B-J Branch pipe connection welds exceeding six in. diameter Volumetric Bli.7 B-J Branch pipe connection velds six in. diameter and smaller Surface Bli.8 B-J Socket velds Surface Bli.9 B-K-1 Integrally velded supports Volumetric Bli.10 B-K-2 Support components Visual.

Bli.11 B-P Exempted components Visual (IWA-5000)

Bli.12 B-G-2 Pressure-retaining bolting Villual Reactor Cooll!llt PU111ps

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B5.l B-G-1 Preusurc-rct1Linlne: boltn nnd ntuds, ln plncc Volumetric B5.2 B-G-l Prl"naurc-rt.*tul 11 tn1~ hol t.11 und atudu

  • vhen rcrnovccl Volumetric nnd-Surrnce B5.3 ll-<l-1 Prcooure-relulr:lni-: bolll111.: Viaunl B5.li ll-K-1 Intct:1*1Llly-wel de<.! uuppor Lo Volumetric B5.5 B-K-:> Support comtHJlll'nt.n Villunl.

B5.6 B-l.-1 Pump cnoi111: vcldu Volumot.ric

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Exwnination .

Category

  • ~'AIJ!J~ 1 cr'.r.G::i 1 COMPDrmN'l'S,PAB'm,AND (Cont'd)

ME'l'llOD:J 01" EXAMINATION Item T1Lblc Bo. IWD-2500 Componcnto and Parts to be Examined Method Reactor Coolant Pumps (Cont'd)

e5.7 B-L-2 Pump casing Vi11ual
e5.8 B-P Exempted components Visual(IWA-5000)

Pump Flywheel Volumetric and Surface Valves

a6.5 B-K-2 Support components Visual
e6.7 B-M-2 Valve bodies Visual
a6.8 B-P Exempted components Visual (IWA-5000)
a6.9 B-G-2 Pressure-retaining bolting Visual

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Itr.m Exnmlnntlon Cutcgor.r Table CJ.Ann 2 TARI.E 2 COMPON~:N'l'::J,l'llH'l'G,llNlJ Ml*~l'l!OlJ Of' EXllMINllTlON No. IWC-2520 Components and PnrLs to be Exnmined Method STEAM GENERJ\TORS Cl.l C-A Circwnferential butt velds Volumetric Cl.2 C-B Hozzle-to-veoscl weldu Volumetric Cl.4 C-D Pressurc-retnining bolting Visual and either surface or volumetric PIPING C2.l C-F ,C-G Circwnferential butt velds Volumetric C2.2 C-F,C-G Longitudin!ll. veld joints in fittings Volumetric C2.3 C-F,C-G Branch pipe-to-pipe weld joints Volumetric C2.4 C-D Pressure-retaining bolting Visual and either surface or volumetric c2.5 C-E-1 lntegrally-velded supports Sur race c2.6 C-E-2 Support components Visual lUIR PUMPS c3.2 C-D Pressure-retaining bolting Visual and either surface or volumetric C3.4 C-E-2 Support components Visual VALVES c4.2 C-D Pressure-retaining bolting Visutil o.nd either surface or volumetric c4.3 C-E-1 Integrally-velded supports Surtace c4.4 c-E-2 Support components *.-Visual

  • TABLE 3 CLASS 3 COMPONENTS Visual Examination In Accordance With IWD-2400 Reactor Coolant Pressurizer Relief Tank Chilled Water System
1. Chillers #11, 12 and 13
2. Chilled Water Strainers
3. No. 1 Expansion Tank
4. Chilled water Pumps Chemical Volume & Control - Operations
1. Re.sin Fill Tank
2. Chemical Volume & Control Tank
3. No. 1 Chemical Addition T!IDk.  :'."*.--
4. Head Tanks 11, 12, 13 and 14
5. No. 1 Boric Acid Batching Tank
6. Boric Acid Tanks 11 and 12
7. Charging Safety Injection Pumps 11, 12 and 13
8. Boric Acid Transfer Pumps
9. Boric Acid Filter
10. No. 1 Reactor Coolant Filter
11. Seal Water Filter
12. Seal Water Injection Filter 11 and 12
13. No. 1 Excess Letdown Heat Exchanger
14. No. 1 Regenerative Heat Exchanger
15. No. 1 Letdown Heat Exchanger
16. No. 1 Seal Water Heat Exchanger
17. Mixed Bed Demineralizers 11 and 12 18 * . Deborating Demineralizers 11 and 12

--- 19. Cation Bed Demineralizer.

20. Boric Acid Blender Chemical Volume & Control-Boric Acid Recovery
1. Hold-Up Tanks 11, 12 and 13
2. No. 1 Concentrates Holding Tank
3. No. 1 Hold-Up Tank Recir. Pump
4. Gas Stripper Feed Pumps 11 and 12
5. Concentrates Holding Tank Transfer Pump 11 and 12
6. No. 1 Concentrates Filter
7. No. 1 Ion Exchange Filter
8. Evaporator Feed Ion Exchangers.11, 12, 13 and 14 *.*
9. Gas Stripper and Boric Acid Evaporator Package

Chemical Volume & Con,ol - Primar Water Recove

1. Monitor Tanks 11 and. 12
2. No. 1 Primary Water Storage Tank
3. Monitor Tank Pumps 11 and 12
4. Primary Water Make-Up Pumps
5. Primary Water Storage Tank Heating Recirc. Pump
6. No. 1 Distillate Filter
7. No. 1 Primary Water Storage Tank Heat Exchanger
8. Evaporator Distillate Demineralizers 11 and 12 Safety Injection
1. Accumulator 11, 12, 13 and 14
2. Boron Injection Tank
3. Refueling Water Storage Tank
4. Safety Injection Pumps 11 and 12
5. Refueling Water Storage Tank Heat Exchanger
6. Refueling Water Storage Tank Heating Water Recirc. Pump Containment. Spray
1. Spray Additive Tank
2. Containment Spray Pump 11 and 12 Auxiliary Feedwater
1. Auxiliary Feed Storage Tank
2. Auxiliary Feed Pump 11 and 12
3. *No. 1 Auxiliary Feedwater Storage Tank Heating Water Circulator Pump
4. No. 1 Feedwater Storage Tank Heat Exchanger Waste Disposal Liquid
1. Waste Monitor Tanks
2. No. 1 Reactor Coolant Drain Tank
  • 3. No. 1 Spent Resin Storage Tank.
4. Waste Monitor - Holdup Tank So Waste Holdup Tank 11 and 12
6. Auxiliary Building sump Tank 7 * . No. 1 Reagent Tank
8. Laundry and Hot Shower Tank 11 and 12
9. No. 1 Chemical Drain Tank**
10. Reactor Coolant Drain Pumps
11. Waste Monitor Tank Pumps *
12. waste Monitor Holdup Tank Pumps
13. Waste Evaporator Feed Pumps*
14. No. 1 Laundry Pump
15. No. 1 Chemical Drain Tank Pump
16. Waste Disposal Filter 17., No. 1 waste Evaporator

Sampling 1.

2.

Volume Control Tank Sample Vessel Boron Sample Tank

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3. Pressurizer Stearn Sample vessel
4. Pressurizer Liquid Sample Vessel
5. Reactor Coolant Sample Vessel
6. Stearn Generator Sample Heat Exchanger 11, 12, 13 and 14
7. Steam Generator Main Steam Sample Heat Exchanger
8. Pressurizer Steam Sample Heat Exchanger
9. Pressurizer Liquid Sample Heat Exchanger
10. Reactor Coolant Sample Heat Exchanger Waste Disposal Solid
1. No. 1 Seal Water Tank
2. Evaporator Bottoms Hold-up Tank
3. Evapcrator Bottoms Trans. Pump 1 and 2
4. Evaporator Bottoms Metering Pump 1 and 2
5. Resin Slurry Metering & .T:t:ci.ns. Pump 1 and 2 1
6. Water Removal Pump 1 and 2
7. Resin Decanter 1 and 2 Component Cooling
1. Component Cooling Surge Tank
2. Component Cooling Pumps 11, 12 and 13
3. Component Cooling Heat Exchangers Residual Heat Removal
1. RHR Heat Exchangers 11 and 12
2. RHR Pumps 11 and 12 Spent Fuel Cooling
1. Spent Fuel Pit Pumps 11 and 12
2. Spent Fuel Pit Skimmer. Pump

3. Refueling Water Purification Pump

4. Spent Fuel Pit Skimmer Filter
5. Spent Fuel Pit Filter
6. Refueling Water Purification Filter
7. Spent Fuel Pit Heat Exchanger (Tube Side)
8. No. 1 Spent Fuel Pit Dernineralizer

Attachment 1 EXCEPTIONS TO ASME BOILER AND PRESSURE VESSEL CODE SECTION XI, NUCLEAR INSERVICE INSPECTION NO. 1 UNIT SALEM NUCLEAR GENERATING STATION The first inservice examination for No. 1 Unit, Salem Nuclear Generating Station, will be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition, up to and including the Summer 1975 Addenda, as re-quired by amendments to Title 10 of the Code of Federal Regulations Part 50.55a, published in the Federal Register on February 12, 1976 and December 6, 1976. Some examinations specified in the Code will not be performed or only partially complied with because of design and construction limitations established prior to the inception of ASME Section XI. In some cas2s, alternate means of inspection will be applied.

Exceptions to the Code are itemized in the attached list. It is the position of PSE&G that the intent of the Code will be complied with, and that the exceptions will not compromise the integrity of nuclear systems.

EXCEPTIONS TO SECTIONI:

INSERVICE EXAMINATION NO. 1 UNIT - SALEM

1. GENERAL 1.1 Required Volumetric, Surface and Visual Examinations of bolt-ing on vessels, pumps, valves and flanges will be performed when they are removed for other reasons. A visual examina-tion will also be performed while the bolting is in place.

It is PSE&G's position that/to remove bolting specifically for Inservice Examination will do more harm to the assembly than the benefits derived from an examination.

1. 2 Visual examination of pump and valve internal pressure boun.d-ary surfaces will only be performed when th'e ..'* internals are removed for other reasons. It is PSE&G's pos'ition that to remove these internals specifically for Inservice Examination will do more harm to the assembly then the benefits derived from an examination.

1.3 There are areas where examinations are restricted due to com-ponents being covered by concrete, wall sleeves, encapsula-tion, hangers, supports and brackets that cannot be removed without requiring extensive work for both removal and rein-stallation. There areas will be identified in the Inservice Examination Plan.

1.4 Ultrasonic Examination of piping wells will be performed in accordance with Article 5 of Section V of the ASME Boiler and Pressure Vessel Code, with the exception that all indi-cations above 100 percent of the reference level shall be investigated to the extent that the operator can evaluate the shape, identity and_location of such refectors.

---:..--~-

2. NUCLEAR CLASS I COMPONENTS 2.1 .Reactor Vessel Code Category Remarks B-B 1. The closure head peel segment to disc circumferential weld is with-.

in the control rod drive shroud and will not be examined volumetrically.

(_ Visual examinations for leaks will be performed during hydrostatic pres-sure tests and leakage tests required by Section XI.

2. The bottom head peel segment to disc.

circumferential weld is within the instrumentation tube cluster, and will not be examined volumetrically.

Visual examinations for leaks will be performed during hydrostatic tests and leakage tests required by Section XI.

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2. NUCLEAR CLASS I COMPONENTS (Cont',d *** )

2.1 Reactor Vessel - Cont'd ***

Code Category Remarks B-B 3. Portions of the meridional welds on the upper and lower heads were not examined due to inter-ference with the CRD shroud on the upper head, and inaccessability with the automated examination device in the lower head. Visual

  • examination .*for leakage will be performed during hydrostatic

. pressure tests and leakage tests requ.ired by Section XI.

Code Category B-D 1. All vessel weld examinations are

/ *(Paragraph IWB-2411) performed from the interior sur-face of the vessel. Due to core barrel design, the inlet nozzles are totally inaccessible from the interior of the vessel when the core barrel is in place. These examinations will be performed

/: when the core barrel is removed during the inspection interval.

~* .------- 2. Due to core barrel design the outlet nozzle examinations can only include the nozzle* inner radius section and the nozzle

  • to vessel weld. These examina-tions are performed from the bore of the nozzle. The vessel base metal will be examined from the I.D. of the vessel when the core barrel is removed during the inspection interval.

Code.Category B-I-1.

(Paragraph IWB-241~.) Due to the core barrel.design the.

cladding in the vessel shell is inaccessible for examination while the core barrel is in place. The visual examination required on chu cladding will be performed when the core barrel is removed during the inspection interval *

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2.3 Steam Gene,tors .e Code Category, Remarks B-F Safe ends on the steam generator nozzles are weld overlays {buttered ends). Ultrasonic {UT) inspection will be limited to examination from the weld surface due to the configuration of the steam genera-tor nozzle and the accoustical properties of the cast material on the elbow side of the weld.

It is not known if radiography can be* performed in service due to radiation. If experience indicates radiography is possible it will be used when examination indicate a need for further volumetric examination.

2.4 Pressure Piping Code Category B-J 1. The longitudinal welds in the cast stainless steel primary loop_ elbows cannot be penetrated by present UT methods. These welds will be examined visually until a UT technique is developed.

  • It is not known if radiography can be performed in service due to radiation. If experience indicates radiography is possible it will be used when examination indicate q need for volumetric examination.

-- 2e . Due to joint configuration and/or cast material of the primary loop elbows, there are welds.where the.

UT examination consisted of only a 55° tranverse {SS 0 T) or a o0 weld

" scan (0°W) and/or 45°T examination from the weld surface. It is not known if radiography can be per-formed 1n service due to radiation.

If experience indicates radiography is possible it will be used when

  • examination indicate a need for further volumetric examination.

These welds will be identified in our Inservice Examination Plan *

. I

.e 2.4 Pressure Piping - cont'd ***

Code Category Remarks B-J 3. Due to anti-whip restraints on the primary loops, portions of several circumferential welds are inacessi-ble. Visual examination for leakage will be performed during hydrostatic tests and leak tests required by Section XI. These welds will be identified in the Inservice Examination Plan.

4. Access to one weld in the safety in-jection piping is restricted by a wall sleeve and it will only be ex-amined visually for leakage during hydrostatic pressure tests and leak tests required by Section XI. This weld will be identified in the In-service Examination Plan.
5. There are a few welds where UT exam-ination is not possible from either 0

sige using shear ~ave. A o w and 45 T or only a 55 T was performed from the weld surface. These welds will be identified in the Inservice Examination Plan. A visual examin-ation for leakage will be performed during hydrostatic pressure tests and leakage tests required by Section XI.

  • B-K-1 60 Two integrally welded pipe supports on a l~ inch nominal pipe size line can not be examined ultrasonically due to pipe thickness, curvature and weld location. Liquid penetrant and visual examinations will be performed in lieu of the ultrasonic method.

These welds will be identified in Inservice Examination Plane

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2.5 Pumps Code Category Remarks B-L-1 The reactor coolant pump casings are cast austenitic stainless steel.

Circumferential welds in the casings cannot be examined by UT because of accoustical properties of the cast stainless. It is not known if radi-ography can be performed in service due to radiation. If experience indicates radiography is possible, the examination will be performed when the pump internals are removed for other reasons. A visual,exam-ination for leakage will be performed during hydrostatic pressure tests and leakage tests required by Section XI.

Code Category B-K-1 The integrally welded pump supports on the reactor coolant pump cannot be examined by UT because of the

  • accoustical properpies of the pump casing. A visual examination will be performed in accordance with Code category B-K-2 until a UT technique is developed.

Code Category

B-G_.:l lo Due to the interference from struc-tural members and piping, there are three (3) reactor coolant.pump bolts that cannot be examined by UT while in place. These bolts will be ex-amined when removed and they will be

.identified in the Inservice Examination Plan.

3. NUCLEAR CLASS II COMPONENTS 3el Paragraph IWC 2412 Pressure Tests and Remarks Visual Examinations* The Pressure Tests and Visual examin-ations will be performed at 110 times design pressure (Pn) for Hydrostatic pressure tests at ~he end of *each in-spection intervale and at se'rvice pressure once every Inspection period.

The above changes will subject these

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  • 3. NUCLEAR CLASS II COMPONENTS (Cont'd.) components to more frequent in-spection than presently required by Code.

3.2 Pressure Piping Code Category Remarks C-F 1. There are several weld joints where access for examination is restricted by non-removable coverings such as excapsulation sleeves, welded hangars, etc. The area around these welds will be examined for any signs of leakage during hydrostatic pressure tests and leakage tests required by Section XI.

These welds will be identified in the Inservice Examination Plan.

2. There are several welds where UT examination is not possible from eiSher side 0 using shear wave. A .

55 T or a o w and or weld surface.

A visual examination for leakage will be performed during hydrostatic pressure tests and leak tests re-quired *by.Section XI. These welds will be identified in the Inservice Examination Plan.

JER,LFL:mds 2-23-77

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    • ATTACHMENT 2 Inservice Inspection Boundary Diagrams 241825Al568 Reactor Coolant 241826A1568 Steam Generator Feed and Condensate 241827Al568 Main Reheat and Turbine Bypass Steam 241828A1568 Chilled Water 241829A1568 Fire Protection 241830A1568 Steam Generator Drains and Blowdown 241831Al568 Chemical Volume & Control - Operation 241832A1568 Chemical Volume & Control - Boric Acid Recovery 241833A1568 Chemical Volume & Control - Primary Water Recovery 241834A1568 Component Cooling 241835A1568 Residual. Heat Removal 241836A1568 Spent Fuel Cooling 241837A1568 Safety Injection 241838A1568 Containment Spray 241839Al568 Auxiliary Feedwater 241840A1568 Waste Disposal Liquid 241841A1568 Service Water - Nuclear 241842A1568 Sampling 241843A1568 Demineralized Water Restricted 241844A1568 Waste Disposal Solid JER,LFL:tb 2-28-77

ENCLOSURE 2 INSERVICE TESTING PROGRAM ASME CODE CLASS 1, 2 & 3 PUMPS NO. 1 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 The following is a tabulation of pumps that are subject to the in-service testing requirements set forth in 10CFR 50.55a(g). The information required in Appendix A of the NRC Staff Guidance For Complying With Certain Provisions Of 10CFR 50.55a(q), "Inservice Inspection Requirements~ is provided herein.

These inservice tests will be performed in accordance with Sub-section IWP of Section XI of the ASME Code, 1974 Edition and Addenda through Winter 1975. This testing program is* applicable for the time period of August 13, 1976 to the start of facility commercial operation.

An inservice test will be run on each pump identified below and a frequency of once per month when the particular component is re-quired to be OPERABLE in accordance with the technical specifi-cations. Testing intervals will be governed by Technical Specifi-cation 4.0.2. Redundant pumps will be tested on a STAGGERED TEST BASIS, as defined in the Technical Specifications.

The* parameters to be measured or observed are also indicated below. Bearing temperature (Tb) on al 1 pumps indicated will be measured annually in accordance with Article IWP-3300 of the Code.

Component Identification Parameters to be Measured or Observed Auxiliary Feedwater Pump, Inlet pressure Nos. 11 and 12~ Differential pressure Flow Rate (1)

Vibration amplitude Lubricant. level

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  • ENCLOSURE 2 (Continued)

Com~onent Identification Parameters to be Measured or Observed Service Water Pump, Nos. Inlet pressure 11, 12, 13, 14, 15 and Differential pressure

16. Flow rate (1)

Vibration amplitude Lubricant pressure Residual Heat Removal Pump, Inlet pressure Nos. 11 and 12. Differential pressure Flow rate Vibration amplitude Lubricant level Chilled Water Pump, Nos. Inlet pressure 11 and 12. Differential pressur~

Flow rate Vibration amplitude Lubricant level Safety Injection Pump, Inlet pressure Nos. 11 and 12. Differential pressure Flow rate Vibration amplitude Lubricant level Containment Spray Pump, Inlet pressure Nos. 11 and 12. Flow rate Vibration amplitude Lubricant level Component Cooling Pump, Inlet pressure Nos~ 11, Y2 and 13~ Differential pressure Flow rate*

Vibration amplitude Lubricant level Charging Pump, Nos. Rotative speed 11, 12 and 13. Inlet press.ure Differential pressure Flow rate Vibration amplitude Lubricant pressure

  • ENCLOSURE 2 (Continued)

Comporient Identification Parameters to be Measured or Observed Boric Acid Transfer Pump, Inlet pressure Nos. 11 and 12. Differential pressure Flow rate (1)

Vibration amplitude Lubricant level (1) Although flow rate determination capability is not presently available, we are in the process of investigating th~ feasibility of utilizing a tran~ducer type electronic flow measuring ~evice.

Demonstration testing is in progress. Upon successful demonstra-tion of the device for this application, it will be installed and utilized to measure flow rate for the Auxiliary Feedwater, Service Water and Boric Acid Tank pumps. It is expected that this equip-ment can be installed and operational by September 1, 1977.

EAL:mlr 2-28-77 T6 1 31-33

  • ENCLOSURE 3 ~

INSERVICE TESTING PROGRAM ASME CODE CLASS 1, 2 AND 3 VALVES NO. 1 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-272 The following is a tabulation of valves that are subject to the in-service tes~ing requirements set forth in 10CFR 50.SSa(g). The information required in Appendix A of NRC Staff Guidance for Comply-ing With Certain Provisions Of 10CFR 50.55a(g), "Inservice Inspection

  • Requirements" is provided herein.

These inservice tests will be performed in accordance with Subsection IWV of Section XI of the ASME Code, 1974 Edition and Addenda through Winter 197 5. Th is testing program is applicable for the time period of August 13, 1976 to the start of facility commercial operation.

Category A Valves The Category A valves identified below will be leak tested during re-fueling outages at the frequency specified in Technical Specification 4.6.1.2 (d). Permissible leakage rates shall be as provided in Tech-nical Specification 3.6.1.2 (b).

The Category A valves identified below will also be full-stroke ex-ercised not more often than once every three months during normal plant operation in accordance Article IWV-3410 of Section XI of the ASME Code, with the exception of those valves marked (1). These valves cannot be operated during normal plant operation and will be full-stroke exercised during Mode 3,4 or 5 operation, not more than once every three months.

Safety Injection System 1SJ53 1SJ60 1SJ123 Component Cooling System 1CC113 1CC117 (1) lCCll 8 (1) 1CC131 (1) 1CC136 (1) 1CC187 (1) 1CC190 (1) 1CC215

',*:' - - -'- - - - _______:: __ ~ ~.~ ..

ENCLOSURE 3 (Continued)

Reactor Coolant System 1PR17 1PR18 Chemical and Volume Control System 1CV3' ltV4 1CV5 1CV7 (1) 1CV116 (1) 1CV284. (1)

Sampling System 1SS27 1SS33 1SS49 1SS64 11SS94 12SS94 13SS94 148594 1SS103 1SS104 188107 188110 Containment Ventilation System lVCl 1VC4 lVC.5 1VC7 1VC8 lVCll 1VC12 Nitrogen Supply System 1NT25

  • 1NT32 Control Air System 11CA330 12CA330 I**,' ,-* 1**' *-, * ...,. '*"I \," 1 .:- ... ..... *t'!," ~' ** "' *:* ** * , ; : *! .

y '

ENCLOSURE 3 (Continued)

Demineralized Water System 1DR29 Steam Generator Blowdown System 11GB4 12GB4 13GB4 14GB4 Fire Protection System 1FP147 Primary Water System 1WR80 CATEGORY B VALVES The Category B valves identified below will be full-stroke exercised not more often than once every three months during normal plant opera-tion in accordance with Article IWV-3410 of Section XI of the ASME Code, with the exception of those valves marked (1). These valves can-not be operated during normal.plant operation and will be full-stroke exercised during Mode 3, 4 or 5 operation, not more o"ften than once every three months. Those valves marked (2) are the dump valves -for rapid closure of the main steam isolation valves (11,12,13 and 14 MS167). These valves will be exercised every three months during normal operation.

Stroke time will not be measured, however, since these are rapid action valves. Acceptable stroke time will be determined when rriain steam iso-lation valve closure times are verified.

Saf et:z: Injection System lSJl ( 1) 1SJ2 (1) 1SJ4 ( l) lSJS ( 1) 1SJ12 (1) 1SJ13 (1) 1SJ30 (1) 11SJ33 ( 1) 12SJ33 (1) llS.140 (1) 12SJ40 (1) 11SJ44 (l)

C_"_**_i-.________________ *,_t._._*_ , _ ._1_*_ _ __.*_*_

....,-_\[*_*,_.,.,,_-*_*l*.'_,,.. _

.. \ ,_,_.11_11*_*_ ..._.. _._,_._*________f-?1_:-,"!"_**~-!_J*

... _ -_*,,,_*.!_~-:----_,_

ENCLOSURE 3 (Continued) 12SJ44 (1) 11SJ45 (1) 12SJ45 ( 1) 11SJ49 ( 1) 12SJ49 (1) 1SJ6'7 ( 1)

., 1sJ68 (1) 1SJ69 (1) 11SJ93 12SJ93 13SJ93 14SJ93 1SJ108 llSJll3 12SJ113 1SJ114 11SJ134 12SJ134 1SJ135 (1)

.££!!!ponent Cooling System I I

11C.Cl5 12CC15 Chilled Water System 1CH30 1CH74 .

1CH151

  • 1CH168 Residual Heat Removal System lRHl (1) 1RH2 (1) 11RH4 (1) l2RH4 * (1) 11RH18 12RH18 11RH19 12RH19 1RH26 (1)

~ ENCLOSURE 3 (Continued)

Auxiliary Feedwater System llAFll 12AF11 13AF11 14AF11 11AF21 12AP2.l 13AF21 14AF21 1AF104 1AF105 1AF106 Containment Spray System 11CS2 (1) 12CS2 (1) 1CS14 (1) 1CS16 (1) 1CS17 (1) 11CS36 (1) 12CS36 (1)

Main Stea~ System 11MS7 (1) 12MS7 (1) 13MS7 (1) 14MS7 (1) llMSlO (1) .

12MS10 (1) 13MS10 (1) 14MS10 (1) 11MS18 (1) 12MS18 (1) 13MS18 (1) 14MS18 (1) 1MS132 11MS167 (1) 12MS167 (1) 13MS167 (.l) 14MS167 (1) 11MS169 (2) 12MS169 (2) 13MS169 (2) 14MS169 (2)

ENCLOSURE 3 (Continued) 11MS171 (2) 12MS171 (2) 13MS171 (2) 14MS171 (.2)

Reactor Coolant System lPSl (1) 1PS2 (1) 1PS3 (1) 1PS4 (1) lPRl 1PR2 1PR6 1PR7 Chemical and Volume Control System 1BR78 1BR79 1BR113 1CV21 1CV27 1CV35 1CV40 (1) 1CV41 ( 1) 1CV48 1CV53 1CV54 1CV55 1CV56 1CV68 * (1) 1CV69 ( 1) 1CV71 (1) 1CV75 1CV77 1CV79 1CV81 1CV82 1CV114 ( 1) 1CV131 ( 1) 1CV132 1CV134 1CV139 1CV140 11CV160 12CV160 1CV172 lCVl 75

ENCLOSURE 3 (Conti:1ued) 1CV179 icv1a*1 1CV185 1CV275 1CV277 (1) 1CV278*

Service Water System 11SW6 12SW6 llSWlO 12SW10 13SW10 14SW10 15SW10 16SW10 11SW17 12SW17 11SW20 12SW20 13SW20 14SW20 11SW21 12SW21 11SW22 12SW22 11SW23 12SW23 1SW26

.11SW39 12SW39

, " ' ' .I '~ '

-s-ENCLOSURE 3 (Continued) 13SW39 11SW42 12SW42 13SW42 11SW52 12SW52 11SW57 i2sw*s7 13SW57

-14SW57 15SW57 11SW58 12SW58 13SW58 14SW58 15SW58 11SW72 12SW72 13SW72 14SW72 15SW72 11SW78 12SW78 1SW81 1SW89 11SW90 12SW90

. 11SW92.

-12SW9 2 13SW92 lSWlOS 11SW122 12SW122 11SW129 12SW129 1SW137

  • 11SW145 12SW145 11SW153 12SW153

. 1SW163 1SW169 1SW175 1SW185 1SW191 1SW199

ENCLOSUF.E 3 (Continued) lSW205 1SW213 1SW913 1SW914 1SW9.15 1SW917 1SW918 1SW91.9 1SW920 lSW921 Sampling System 11SS93 12SS93 13SS93 14SS93 Main Feedwater System 11BF19 (1) 12BF19 (1) 13BF19 (1)

,14BF19 (1) ilB.F40 (1) 12BF40 (1) 13BF40 (1) 14BF40 (1)

Containment Ventilation System 1VC2 1VC3 1VC6 1VC9 lVClO 1VC13 1VC14 Service Air Svstem SA118

ENCLOSURE 3 (Continued)

Refueling Canal 1SF22 1SF36 Category C Valves The Category C check valves identified below will be full-stroke execised not more often than once' every three months, during normal plant operation in accordance with Article IWV-3520 of Section XI of the ASME code, with the exception of those valves marked (1).

These valves cannot be exercised during normal plant'operation and will be full-stroke exercised during Mode 5 or 6 operation~ not more of ten than once every nine months.. Those valves marked (2) w il 1 be exercised during Mode 5 or 6 operation when relief valve 1CV241 has been removed for t~sting.

The Category C safety/relief valves identified below will be bench

  • tested with suitable hydraulic or pneu~atic equipment in accordance*

with Article IWV-3510 of Secticin XI 0£ the ASME Code. Those valves marked (3) will be tested in place with hydraulic or pneumatic assist equipment. Test frequencies will be determined in accordance with

_Table WV-3510-1.

§afety Injection System Check Valves Safety/Relief Valves 1SJ3 lSJlO 11SJ17 ( 1) 11SJ29 12SJ17 ( 1) 12SJ29 13SJ17 ( l) 13SJ29 14SJ17 ( 1) 14SJ29 1SJ31 1SJ32 11SJ34 (1) 11SJ39 12SJ34 ( 1) 12SJ39 11SJ43 (1) 11SJ48 12SJ43 ( l) 12SJ48

-i3sJ43 {l) 14SJ43 (1) 11SJ55 (1) 12SJ.55 (1) 13SJ55 (1) 14SJ55 ( 1) 11SJ56 ( 1) 12SJ56 (1) 13SJ56 (1)

ENCLOSURE 3 (Continued)

Check Valves Safety/Relief Valves 14SJ56 ( 1) 1SJ70 ( 1) 1SJ107.

11SJ139 ( 1) 12SJ139 ( 1) 13SJ139 (1) 14SJ139 ( 1) 11SJ144 ( 1) 12SJ144 (1) 13SJ144 ( 1) 14SJ144 ( 1) lSJlSO (1) 11SJ156 (1) 12SJ156 (1) 13SJ156 ( 1) 14SJ156 ( 1)

ComEonent Coolin9 System Check Valves Safety/Related Valves llCCl 11CC14 12CC1 12CC14 13CC1 1CC34 1CC109 1CC40 1CC137 (1) lCCSl 1CC317 (1) 1CC58 1CC320 (1) 1CC63 1CC68 1CC75 1CC81 1CC112 11CC129 12CC129 13CC129 14CC129 1CC135

.1CC138 1CC147 1CC156 1CC162 1CC165 1CC170 1CC193 lCC.212

ENCLOSURE 3 (Continued)

Chilled Water System Check Valves Safety/Relief Valves liCH13 12CH13 1CH61 Residual Heat Removal System Check Valves Safety/Relief Valves 11RH8 (1) 1RH3 12RH8 (1) 13RH27 (1) 14RH27 (1)

Auxiliary Feedwater System Check Valves Safety/Related Valves 11AF4 (1) 1AF99 12AF4 (1) 1AF128 13AF4 {l) 11AF8 {l) 12AF8 (1) 13AF8 (1) 11AF2 3 (1) 12AF23 (1) 13AF23 (1) 14AF23 (1)

Containment Spray System Check Valves Safety/Related Valves 11CS4 {l) _llCSS

-12CS4 (1) _12CSS 11CS21 (1) 1CS26 12CS21 (1) 11CS48 (1) 12CS48 (1)

ENCLOSURE 3 (Continued)

Main Steam System Check Valves Safety/Relief Valves llMSll (3) 12MS11 (3}

13MS11 (3) 14MS11 ( 3) 11MS12 (3) 12MS12 (3) 13MS12 (3)

  • 14MS12 (3) 11MS13 (3) 12MS13 (3) 13MS13 (3) 14MS13 (3) 11MS14 ( 3) 12MS14 ( 3) 13MS14 (3) 14MS14 (J) 11MS15 ( 3) 12MS15 (3) 13MS15 ( 3) 14MS15 (3)

Reactor Coolant System Check Valves Safety/Relief Valves 1PR25 1PR3 1PR4 lPRS Chemical and Volume Control System Check Valves Safety/Relief Valves 1BR99 11BR81 11BR152 ( 2) .12BR81 12BR152 (2) 13BR81 13BR152 (2) 1CV6 1CV23 (1)

  • 1cv43 1CV36 (1) 1CV115 1CV42 (1) 1CV124 1CV47 1CV141 1CV52 1CV241 1CV63 1CV253

' .*. f"'"I r ' ,

ENCLOSURE 3 (Continued)

Check Valves Safety/Related Valves 1CV74 (1) 11CV99 (1) .

12CV99 (1) 13CV99 (1)

  • 14CV99 (1) 1CV135 1CV13 7.

1CV147 11CV154 12CV154 1CV173 1CV176 ( 1) 1CV180 1CV183 1CV189 1CV196 (1) 1CV198 (1) 1CV275 Service wat~r System Check Valves Safety Related Valves 11SW2 1SW109 12SW2 11SW242 13SW2 12SW242 14SW2 13SW242 15SW2 14SW242 16SW2 15SW242 11SW5 12SW5 (1) 13SW5 14SW5 (1) 11SW13

  • .. 12SW13

'13SW13 14SW13 15SW13 16SW13 11SW34 12SW34 11SW36 12SW36 11SW38 12SW38

  • 11SW44 (1) 12SW44 (1)
  • ENCLOSURE 3 (Continued)

Check Valves Safety/Relief Valves 13SW44 (1) 11SW47 12SW47 llSWSl 12SW51 11SW53 12SW53 11SW77 (1) 12SW77 (1) 11SW79 (1) 12SW79 (1) 11SW99 12SW99 13SW99 Nitrogen Supply System Check Valves Safety/Relief Valves 1NT26 1NT15 frimary Water System Check Valves Safety/Relief Valves 1WR81 :iwR123 Category E Valves No regular testing requirements will be imposed upon Category E valves.

Operational checks, with appropriate record entries, shall be performed and the posit ion of these valves sh al 1 be verified and recorded before operations are performed and after operations are completed. V~rifi cation shall be made that each valve is locked or sealed in its re-quired position.

  • safety Injection System 11SJ16 12SJ16 13SJ16 14SJ16 1SJ71 11SJ138 12SJ138 13SJ138 14SJ138
  • ENCI.OSURE 3 (Continued)

Residual Heat.Removal System llRHlO 12RH10 11RH14 12RH14 Containm~nt Spray System llCSl 12CS1 11CS6 12CS6 11CS20 12CS20 Chemical and Volume Control System 11BR101 12BR101 13BR101 11BR151 12BR151 13BR151 1CV44 1CV49 1CV57 1CV64 11CV98 12CV98 13CV98 14CV98 Service Water System llSWl 12SW1 13SW1 14SW1 15SW1 16SW1 11SW3 12SW3 13SW3 14SW3 15SW3

  • ENCLOSUF.E 3 (Continued) 16SW3 11SW9 12SW9 llSWll 12SW11 13SW11 14SW11 15SW11 16SW11 11SW12 12SW12 13SW12 14SW12 15SW12 16SW12 1SW104 11SW127 12SW127 11SW134 12SW134 1SW142

_llSW150 12SW150 11SW158 12SW158 1SW168 1SW174 1SW180 1SW196 1SW204 1SW210 1SW218 SPECIAL VALVES The valves identified below are of a special nature in that they do not lend themselves to the test requirements set forth for the specific categories of valves in Subsection IWV of Section XI of the ASME Code, althciugh they are deemed to be subject to the inservice testing requirements of 10CFR50.55a. These valves will be demonstrated to be OPERABLE in the manner outlined below.

Service Water System 11SW8 These valves are service water pump cooling header modulating 12SW8 pressure control .valves, supplying service water to the

  • ENCLOSURE 3 (Continued) service water pump motor upper bearing oil coolers. The valves operate continually in the course of nor~al plant operation. Satisfactory operation of these valves will be determined by observance of the proper operating tem-peratures of the service water pump motor upper bearing oil. A bearing oil temperature alarm is provided in the Control Room.

11SW49 These valves are modulating, pressure controlled service 12SW49 water header bypass valves which operate to maintain 11SW305 correct pressure in the service water headers. The valves 12SW305 are continually operable in the course of normal plant operation. Satisfactory operation of these valves wiJl be determined by observance of the proper operating pressure in the service water headers. Service water header pressure and bypass valve actuation alarms are provided in the Control Room.

11SW223 These valves are the service water outlet isolation valves 12SW223 for the containment fan cooler units. They are automatically 13SW223 positioned by the fan cooler control circuits, depending on 14SW223 the mode of operation selected. Proper operation of these 15SW223 valves will be verified during surveillance testing of the fan. cooler units in accordance with Technical Specification 4a6.2.3, Verification of proper operation will be meeting the Technical Specification flow requirements.

EAL:mlr 2-28-77 T6 1 39-56

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