ML18096A877

Vol 1 of 1990 Inservice Examination of Selected Components at Salem Generating Station,Unit 2.

ML18096A877
Person / Time
Site:	Salem
Issue date:	08/06/1992
From:	Public Service Enterprise Group
To:
Shared Package
ML18096A876	List: ML18096A875 ML18096A877
References
NUDOCS 9208120181
Download: ML18096A877 (28)

Text

FORM NIS-*OWNER 1 S DATA REPORT FOR I.RVICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner:; Public Service Electric & Gas Co.,.80 Park Plaza Newark, N.J-. 07101 *

2. Plant:5}'i~t.$.~em Generating Station P.O. *Box E

• 'B;Jt~ncock's Bridge, N.J. 08038

3. Plant:.:'.'~"~11nit 2

4. owner*s~fcertificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

8. This report is for the second examination conducted in the third inspection period which ended October 13, 1991. This examination completes the first inspection interval which was from October 13, 1981 to October 13, 1991.

9. Components inspected:

MANUFACTURER STATION* OR COMPONENTS OR MANUFACTURER OR INSTALLER PROVINCE. NATIONAL

. APPURTENANCE OR INSTALLER SERIAL NO. NUMBER BOARD NO.

.. . .~

1. 2 Reactor Combustion 67201 Head N/A 20765 Vessel Engineering- 67101 Vessel I 21 Steam Westinghouse *1201 .N/A .

Generator Tampa Div. '.:-r"**.

P.O. BOX 19218 Tampa, Fl.

33616

1. 22 Steam II II 1202 N/A 68-44' Generator

1. 23 Steam II II 1004 68-11 Generator

1. 24 Steam 1204 N/A 68-52 Generator *-

" "

Pressurizer Delta Southern 1211 N/A 68-48 I

Page 1 of 25

,r-='"'920S120181 920806' ~

.

• PDR* ADOCK 050003\1 _* . *. J.

I G.. . * ... _PDR .* ' '

FORM NIS~WNER'S DATA REPORT FOR !~VICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101

2. Plant: ._.Salem Generating station P.O. Box E

• .:Hancock's Bridge, N. J. 08038 J. Plant: __'Unit 2

4. owner' s*iCertif icate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

9. Components inspected (continued):

MANUFACTURER STATION OR COMPONENTS OR MANUFACTURER OR INSTALLER PROVINCE NATIONAL APPURTENANCE OR INSTALLER SERIAL NO. NUMBER BOARD NO.

Chemical & United N/A N/A N/A Volume Engineers &

Control Constructors Piping System (UE&C) JO ~. :-: : .

South 17th st.

Philadelphia, *:.:\

Pa. 19101 ,~,,,

~J Main Steam UE&C N/A N/A Ni/A Piping System Pressurizer Relief Piping UE&C N/A . N/A N/A System Reactor UE&C N/A N/A N/A Coolant Piping System Safety UE&C N/A N/A N/A Injection Piping System

/

Page 2 of 25

FORM NIS~)WNER'S DATA REPORT FOR I1~RVICE INSPECTORS AS REQU~D BY THE PROVISIONS OF THl9ASME CODE RULES

1. Owner: Public Service Electric & Gas co., 80 Park Plaza Newark, N.J. 07101

2. Plant:. ~alem Generating Station P.O. Box E

• ,!J.(~ncock's Bridge, N.J. 08038

3. Plant::;~:);Jnit 2

4. owner**s.:*certificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

10. Abstracts of Examinations:

This report also contains augmented examinations required by Salem Technical Specifications and Regulatory Guides, Circular, and Bulletins issued by the United States Nuclear Regulatory Commission.

Examinations were conducted by PSE&G as well as companies under contract to PSE&G. The following is a brief summary with further details found in the attached report and on file at the Salem Generating Station.

Since nearly all inservice examination requirements can be f.ound in Salem's Technical Specifications, this summary lists'* these requirements first arranged according to Tech. Spec. paragraph number followed by applicable NRC circular and bulletins.

• P~ge 3 of 25

FORM NIS.WNER'S DATA REPORT FOR I.RVICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas co., 80 Park Plaza Newark,

. N.J. 07101

. 2* Plant :'.;J;~~-. ~~lem Generating Station P. 0. Box E

. lJl;*l;lJ.ncock' s Bridge, N. J. 08 o3 8 3* Plant :1*"'Unit 2

4. owner'~~l"certificate of Authorization (if required) N/A.

5. commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

11. Examination Summary:

11.1 Technical Specification .4.0.5 - ASME Section XI The examinations conducted during the sixth refueling/ten year ISI Outage at Salem Unit 2, complete the examination required for the first ten year inspection interval.. The components were examined in accordance with "Examination Plan for the 1992 Inservice Examination* of Salem Generating Station, Unit 2 11

• 11.* 1.1 ISI Examination

.-~

11.1.2 Southwest Research Institute ( SwRI) under< the ;§.1'.

direction of the Salem ISl Group conducteci,on4 hundred (100) ultrasonic, twenty seven (2-1}"liquid penetrant, three (3) magnetic particle, and ten (10) visual examinations. The examinations were conducted on the following-welds and components:

Class 1 Vessels

- Reactor Pressure Vessel (RPV)

Piping

- Chemical and Volume Control System

- Reactor Coolant system

- Safety Injection System:

Pumps

- Reactor Coolant Pump #.21, 22 and 23 Flywheels Valves

< Pressurizer Relief Systein i

.1 Page 4 of 25

FORM NIS-eoWNER'S DATA REPORT FOR I.RVICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N .. J. 07101

2. Plant:;o ..:--.J~~lem Generating Station P.O. Box E

i~

• J!~ncock' s Bridge, N. J. 08038

3. Plant: *T:Jnit 2 4.. owner*s{Certificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

11. Examination Summary (continued):

Class 2 Vessels

- Steam Generator # 21 Piping

- Chemical and Volume Control system

- Main Steam System

- Pressurizer Relief System Valves

- Main Steam System 11.1.3 UT examination of # 21 Steam Generator transition cone to shell weld as required by ASME Section;'XI and PSE&G response to I.E. Notice 9 0-04 *

• 11.1.4 Automated UT (AUT) examinations were performed on the Reactor Vessel welds and selected.reactor coolant piping welds from the inside surf ace utilizing the PaR ISI-2 Device with Fast. PaR and Enhanced Data Acquisition System (EDAS) equipment.

The examinations were performed in accordance with the 74/S75 Edition of ASME Section XI.

11.1.5 Automated UT examinations were conducted on the outlet nozzle to shell and associated butt welds from the inside surface to fulfill the second interval first inspection period requirements in accordance with the 1986 Edition of ASME Section XI.

11.* 1. 6 Remote UT,- ET and VT examinations were performed on the-core barrel using the PaR*device on linear indication # 4 (CNF 90-1) that was identified the previous outage during remote visual (VT) of the reactor vessel. There were no reportable indications.

I 11.1.7* The following recordable indications were reported during the course of the examinations.

A. The UT examination of 21-STG-TCSC (# 21 Steam Generator transition cone to shell) revealed Code allowable inclusions which were documented on CNF 1.

Page 5 of 25

FORM NIS~WNER'S DATA REPORT FOR I~VICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101 2* Plant ::::r,~;f .!?.~tlem Generating Station P. o. Box E

.:,11~ncock's Bridge, N.J. 08038

3. Plant:.:::~.~.Unit 2

4. owner's/Certificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

11. Examination Summary (continued):

B.*UT examinations.of butt welds 29-RCN-1230-1 and 29-RCN-1220-1 (29 11 reactor coolant piping) revealed Code allowable spot indications reported on CNF's 5 and 6, respectively. All UT indications were excepted "as is" by* PSE&G.

c. PT examination of 27.5-RC-1210-1/4-PS-1211 (27.5 11 reactor coolant pipe branch connection} revealed a 1/4" linear indication reported*on CNF 2.

Reexamination after a cosmetic surf ace __

preparation revealed no recordable indicat~~ns.

• if 11.1.8 There were no other reportable indications identified during this ISI.

11.2 Visual Examination of Supports 11.2.1 Contract personnel under the direction of the Salem ISI Group conducted visual examinations on two (2)

Nuclear Class o, forty three (43) Nuclear Class I, forty eight (48) Nuclear Class II and three hundred and eight (308) Nuclear Class III supports.

There were several minor discrepancies noted including; wrong spring settings, rust, loose bolts, etc ** Work orders and/or deficiency reports were generated to document and correct all discrepancies.

As a result of some of the discrepancies, seventeen (17) additional support exams were scheduled and performed satisfactory.

I I

Page 6 of 25

FORM NIS-~WNER'S DATA REPORT FOR I~RVICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101

2. Plant: ~c- ~~lem Generating Station P. o. Box E

~ ~~ncock's Bridge, N.J. 08038

3. Plant:' - Unit 2

4. Owner's Certificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit:* N/A

7. Examination Dates: 06/25/90 through 5/10/92

11. Examination Summary (continued):

11.3 Ten Year ISI Hydrostatic Test Program 11.3.1 Approval for the use of Code case N-498 (Alternative Rules for 10-Year Hydrostatic Testing for Nuclear Class 1 and 2 SystemsSection XI, Division 1) was obtained for the Salem Unit 2 sixth refueling outage. Forty one (41) Code Case N-498 system pressure tests were completed on various Nuclear Class I and II systems. In addition, sixty (60) hydrostatic tests were completed on Nuclear Class 3 systems. These system pressure tests were completed on Auxiliary Feedwater, Control Air, Component-:;i.

Cooling, Chilled Water, Containment Spray; Ch~ical and Volume Control, Demineralized Water, Fire -

Protection, Reactor Coolant, Residual Heat Removal, Station Air, Steam Generator Feed, Safety Injection, Sampling, service water, Ventilation, Waste Liquid, and primary Water systems. All hydrostatic tests and system pressure tests were performed in accordance with 1974/Summer of 1975 Edition of ASME Section XI and Code Case N-498.

11.3.2 Below is a summary of notable leaks detected on systems during conduct of pressure tests and corrective action taken:

A. A 3/8" Service Water, Nuclear Class III, instrument line socket weld was weeping. A deficiency report was initiated. The weld was repaired and tested satisfactorily.

B. A 3/4" Nitrogen supply to the Accumulators, Nuclear Class II, 90° elbow was found leaking during a Code Case N-498 system pressure test at inominal operating pressure. A deficiency report was initiated. The leak was repaired and tested satisfactorily.

I Page 7 of 25

FORM NIS-~WNER'S DATA REPORT FOR I~RVICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101

2. Plant: Salem Generating Station P.O. Box E Hancock's Bridge, N.J. 08038

3. Plant: Unit 2

4. Owner's Certificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

11. Examination Summary (continued):

c. A 3/4" Component Cooling supply to # 22 Reactor Coolant Pump lower motor bearing cooler, Nuclea~

Class III, was found leaking during a hydrostatic test. A deficiency report was initiated. The leak was repaired and tested satisfactorily. The other three (3) Reactor Coolant Pump cooling water lines were inspected and preventive maintenance performed.

D. A 4" Service Water chilled water outlet header, Nuclear Class.III, was found leaking during a hydrostatic test. A deficiency report was .:

initiated. The leak was repaired and retested satisfactorily.

11.4 System Pressure Tests 11.4.1 Summary A. System leakage exams were performed in accordance with ASME Section XI on all Nuclear Class I systems.

B. System functional tests/system inservice tests were performed on those Nuclear Class II and III systems required to fulfill the requirements of the third inspection period.

? *-*

11.4.2 Results None of the systems tested exhibited any excessive leakage. There was some minor mechanical leakage which was identified and Work Orders were written to correct the discrepancies.

I I

!

Page 8 of 25

FORM NIS~WNER'S DATA REPORT FOR I~RVICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ~SME CODE RULES

1. Owner: Public Service Electric & Gas Co., so Park Plaza Newark, N.J. 07101

2. Plant: Salem Generating Station P.O. Box E

-H~ncock's Bridge, N.J. 08038

3. Plant: -'Unit 2

4. owner's c'ertificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

11. Examination summary (continued):

11.5 Technical Specification 4.4.6.0 - steam Generator Tube Eddy Current Inspection.

11.5.1 The original eddy current examination scope is detailed below:

A. Six (6%) Tech. Spec. bobbin coil examination in #

21 Steam Generator (204 tubes).

B. Six (6%) Tech. Spec. bobbin coil examination in #

23 Steam Generator (204 tubes). -;-...j~

c. A non-tech spec. sample of one thousand five hundred and thirty five (1,535) tubes in # 21 Steam Generator to try and comply with EPRI recommended examination guidelines_ of performing 100% examination of all steam generator tubes over a six year period. This sample combined with the Tech. Spec. sample brings the total percentage of tubes inspected in this generator for this outage to 52%.

D. A non-tech spec. sample of one thousand six hundred and forty seven (1,647) tubes in # 23 Steam Generator to try and comply with EPRI recommended examination guidelines of performing 100% examination of all steam generator tubes over a six year period. This sample combined with the Tech. Spec. sample brings the total percentage of tubes inspected in this generator for this outage to 55%.

E. A 50% (1,694 tubes) inspection in # 21 Steam Generator with rotating pancake probe to address i the concern of Expansion Zone Pure Water Stress Corrosion Cracking at the hot leg tube sheet (WEXTEX) for steam generators manufactured using explosive tube expansion techniques.

Page 9 of 25

FORM NIS.OWNER'S DATA REPORT FOR I.RVICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101

2. Plant: Salem Generating station P.O. Box E ila-ncock's Bridge, N.J. 08038

3. Plant: Unit 2

4. Owner's Certificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

11. Examination summary (continued):

F. A 50% (1,694 tubes) inspection in # 23 Steam Generator with rotating pancake probe to address the concern of Expansion Zone Pure Water Stress Corrosion Cracking at the hot leg tube sheet (WEXTEX) for steam generators manufactured using explosive tube expansion techniques.

11.5.2 The results of the eddy current inspections are as follows:

A. The Tech. Spee. sample in # 21 Steam Generator revealed no indications equal to or exceeding the plugging limit and satisfied the less than 5% of the inspected tubes being degraded, therefore no scope expansion was required.

B. Six (6) tubes with indications from previous refueling outages were plugged due to indication growth which either exceeded the Tech. Spec.

plugging limit or for preventive maintenance purposes due to the tube being degraded to the 35

- 39% through wall range.

c. The Tech. Spec. sample in # 23 Steam Generator revealed no indications equal to or exceeding the plugging limit and satisfied the less than 5% of the inspected tubes being degraded, therefore no scope expansion was required.

D. One (1) tube in the non-tech spec. sample in # 21 Steam Generator was preventively plugged due to tube degradation in the 35 - 39% through wall range.

E.i There were no tubes plugged in the non-tech spec.

sample in # 23 Steam Generator.

F. One (1) tube was plugged due to a single axial indication noted during the RPC inspection on #

21 steam Generator. The indication was estimated to exceed the 40% plugging limit.

Pa<;e 10 of 25

FORM NIS-9:>WNER'S DATA REPORT FOR Ii9RVICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N .J. 07101

2. Plant: Salem Generating Station P.O. Box E Hancock's Bridge, N.J. 08038

3. Plant: - Unit 2

4. Owner's Certificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

11. Examination Summary (continued):

G. There were no tubes plugged in # 23 Steam Generator as a result of the RPC inspection.

11.5.3 Additional Steam Generator work performed this outage.

As a response to NRC Bulletin 88-02, "Rapidly Propagating Fatigue Cracks in Steam Generator Tubes", and as a consequence of the steam generator tube rupture event at Virginia Power's North Anna Unit 1 plant, an*engineering evaluation was .

completed to identify potential ~ubes subject to vibration induced fatigue. Eight (8) tubes were identified as being susceptible to this phenomenon and were removed from service through the installation of a cable type tube dampener with a mechanical plug in the hot leg and a sentinel plug in the cold leg. The sentinel plug allows early identification of primary to secondary leakage.

-: :~- -*._-

Page 11 of 25

FORM NIS_.,WNER'S DATA REPORT FOR !~VICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101

2. Plant: Salem Generating Station P.O. Box E Hancock's Bridge, N.J. 08038

3. Plant: Unit 2

4. Owner's Certificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

11. Examination Summary (continu~d):

11.5.4 Results of eddy current examination are as follows:

Steam Extent of No. of Tubes Tubes with Indications Generator Examination Ins12ected < 2oi 20-39i > 4oi 21 Full Length 1,739 16 40 1 Bobbin coil RPC at 7 0 0 0 Support Plates RPC of 1,694 0 0 1 Tubesheet

---

23

---

Full Length

---

1,851

---

~

36 26 0 Bobbin Coil RPC at 46 0 0 0 Support Plates RPC of 1,694 0 0 0 Tube sheet Sub-Total Full Length 3,590 52 66 1 Support Plates 53 0 0 0 Tubesheet 3,388 0 0 1

---

TOTAL 7,031 52 66 2 Page 12 of 25

FORM NIS--WNER'S DATA REPORT FOR I~9rtvICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas co., 80 Park Plaza Newark, N.J. 07101

2. Plant: Salem Generating Station P.O. Box E Hancock's Bridge, N.J. 08038

3. Plant: Unit 2

4. owner's Certificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

11. Examination Summary (continued):

11.5.5 Current Status of Steam Generators At this time, the total number of tubes plugged in the Salem Unit 2 Steam Generators are as follows:

Generator # 21 22 23 24 112 105 112 111 NOTE: The first five and the last five tubes of Row 1 in each*of the Steam Generators were mechanically plugged due to a wear probiem on the tubes caused by a vibration in the tube lane blocking device. The remaining Row 1 tubes were preventively plugged due to the onset of stress corrosion cracking in the U-bend region as evidenced in two of the four steam gene.raters.

11.6 Technical Specification 4.6.1.2 (a) Reactor Containment* Type "A" Test 11.6.1 Summary The Third and Final Inservice Containment Integrated leak Rate (Type A) Test for the first 10-year interval was performed during the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period ending March 24, 1992. The test was coordinated and directed by the Salem ISI Group.

1.t:;,;.6. 2 Results

• The test results indicate the As-Left Integrated Containment Leakage Rate, including corrections, at o *.0224% per day of containment free volume at 95%

• upper confidence level. This is in accordance with the acceptance criteria prescribed in 10CFR50, Appendix J and Salem Unit 2 Technical Specifications. The calculated As-Found leakage rate was 0.03196% per day which is also within the prescribed limits of 0.075% per day in 10CFR50, Appendix J.and 0~1% per day in Tech. Specs.

Page 13 of 25

FORM NIS.OWNER'S DATA REPORT FOR I.RVICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas co., 80 Park Plaza Newark, N.J. 07101

2. Plant: Salem Generating Station P.O. Box E Hancock's Bridge, N.J. 08038

3. Plant: Unit 2

4. owner's Certificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

11. Examination Summary (continued):

11.7 Technical Specification 4.6.1.2d, Containment Type "B" (Penetrations) and Type "C" (Valves) Leak Rate Testing.

11.1.1 Summary The PSE&G Research Corp. under the field supervision of the Salem ISI Group, conducted local leak rate tests on sixty three (63) Type "B" Electrical Penetrations, seven (7) Type "B" Mechanical Penetrations and fifty five (55) Type "C" Mechanical Penetrations (113 valves).

11. 7. 2 Results A. Several Type "C" valves exceeded the recommended leak rate acceptance criteria. These valves were reworked to an acceptable condition and retested satisfactorily.

B. A total As-Found leakage of 40,064.8 SCCM was measured through all Type "B" and "C" containment penetrations. After corrective maintenance, a total As-Left leakage of 31,427.3 SCCM was measured thrqugh all Type "B" and "C" penetrations.

11.s Technical Specification 4.6.l.3b Elevation 100 1 and 130 1 Airlock Leak Rate Tests 11.s.1 summary PSE&G Research and Test Lab under the field supervision of the Salem ISI Group conducted leak rate tests on the 100 1 and 130' containment personnel airlocks.

Page 14 of 25

FORM NIS-~WNER'S DATA REPORT FOR  !~~VICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas co., 80 Park Plaza'Newark, N.J. 07101

2. Plant: Salem Generating Station P.O. Box E Hancock's Bridge, N.J. 08038

3. Plant: Unit 2

4. owner's Certificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

11. Examination summary (continued):

11. 8. 2 Results The combined As-Found leakage for these airlocks was 6,890.0 SCCM. After maintenance, the combined As-Left leakage for the airlocks was 4,036.0 SCCM.

Both of these measured combined leakage rates satisfy the Technical Specification acceptance criteria of~ 0.05 La (10,812 SCCM).

11.9 Technical Specification 4.6.1.6.1 Containment Surfaces 11.9.1 summary A general inspection of containment accessible interior and exterior surfaces was completed prior to the Integrated Containment Leakage Rate Test as r,equired by ISI procedure S2. SS-IS. ZZ-0005 (Q) .

11. 9. 2 Results A. The visual inspection of the exterior surfaces was satisfactory with no indications noted.

B. The visual inspection of the interior surface revealed minor corrosion on the liner at 78' elevation. A Deficiency Report (DR) was initiated by the ISI group IAW Nuclear Department Administrative Procedure NC.NA-AP.Zz-0020, Nonconformance Program. The DR was dispositioned that this condition did not constitute a deficiency and no further corrective action was required at this time. The disposition also referenced Engineering Evaluation S-2-ZZ-SEE-0676-0.

Page 15 of 25

FORM NIS-e:,WNER'S DATA REPORT FOR I.RVICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101

2. Plant: Salem Generating Station P.O. Box E Hancock's Bridge, N.J. 08038

3. Plant: Unit 2

4. owner's- Certificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

11. Examination Summary (continued):

11.10 Technical Specification 4.7.9 (a) Visual Inspection of Hydraulic and Mechanical Snubbers 11.10.1 Summary Contract and PSE&G personnel under the direction of the Salem ISI Group conducted visual examinations on one hundred and twelve (112) mechanical snubbers and twenty four (24) hydraulic snubbers.

11.10.2 Results A. One mechanical snubber, 2S-23FWSN-017B, was found with a spherical bearing out of alignment. This snubber subsequently failed a stroke test. The failure was classified as a visual examination failure and the unit was replaced. An engineering evaluation was performed analyzing the snubber acting as a rigid restraint and it was determined that system pipe loads and stresses remained within Code allowable and design margin limits. As a result of this failure, the visual examination frequency for medium size snubbers has been increased from once every eighteen (18) months to once every twelve (12) months +/- 25%.

B. There were no other discrepancies noted which would affect snubber operability. There were some minor items were noted including reservoirs not full, missing washers, loose spherical bearings and binding around the bearings. These conditions were all noted and corrected.

C.1 One mechanical snubber, 2C-SISN-009, found frozen was replaced with a hydraulic snubber.

D. All snubbers which were removed and reinstalled

. received an "As-Left" visual examination.

Page 16 of 25

FORM NIS~WNER'S DATA REPORT FOR Il~VICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101

2. Plant: Salem Generating Station .P.O. Box E Hancock's Bridge, N.J. 08038

3. Plant: Unit 2

4. owner's Certificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

11. Examination Summary (continued):

11.11 Technical Specification 4.7.9 (c) "Functional Testing of Selected Hydraulic and Mechanical.snubbers" 11.11.1 Summary - Hydraulic snubbers Per Technical Specifications, 10% of the installed hydraulic snubbers as well as all previous outage functional test failures are required to be tested.

The 10% sample included one (1) 200 kip Main Steam snubber and two (2) 1000 kip Steam Generator snubbers. There.were no previous outage test failures. In addition, due to work on the Main Steam isolation valves, the remaining seven (7) 200 kip snubbers were also functionally tested.

11.11.2 Results - Hydraulic Snubbers There were noted discrepancies in the Tech. Spec.

sample or in the additional tests performed on the remaining 200 kip snubbers.

11.11.3 Summary - Mechanical Snubbers Per Technical Specifications, 10% of the total installed mechanical snubbers as well as previous outage functional test failures were tested utilizing the WYLE Model 150 Snubber Testing Machine. The 10% sample is broken down by snubber category size (small and mediums) with 10% from each size selected each outage. All selected snubbers are detailed below:

A. The 10% sample of the medium size snubbers included three (3) PSA-l's, three (3) PSA-3's and

,three (3) PSA-lO's.

B. Due to previous outage failures, 100% of the small size snubbers (PSA-l/4's, PSA-l/2's and equiv. hydraulic snubbers) are tested each outage. This resulted in tests being performed on nineteen (19) Model 1/4's and three (3) Model 1/2's.

Page 17 of 25

FORM NIS--OWNER'S DATA REPORT FOR I.RVICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas Co., 8.0 Park Plaza Newark, N.J. 07101

2. Plant: Salem Generating station P.O. Box E Hancock's Bridge, N.J. 08038

3. Plant: Unit 2

4. Owner's Certificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

11. Examination Summary (continued):

c. Two (2) previous outage test failures, a PSA-3 and a PSA-10 were also selected for testing.

D. One additional PSA-3, 2S-23FWSN-017B, was also selected for testing due to a failed visual examination during this outage.

11.11.4 Results - Mechanical Snubbers A. All the medium size Tech. Spec. sample snubbers were tested satisfactory.

B. Five small size snubbers tested had high break-away and running loads, however, they still met acceptance criteria. One PSA-1/2, 2A-SISN-105A, failed its functional test and was replaced.

Snubber 2C-SISN-009 was found frozen. A review of the history on this snubber showed previous failures so it was replaced with a hydraulic snubber. Neither of these failures required a sample expansion due to 100% functional testing.

c. The two medium previous test failure medium size snubbers passed.satisfactorily.

D. The snubber that failed its VT also failed a functional test and was replaced. No sample expansion.on medium size snubbers was made because it was not part of the original sample plan and had already been declared a failure from the visual examination.

11.12 NRC Circular 76-06 and NRC Bulletin 79-17 "Commitment to Examine and/or Flush Stainless Steel Lines Containing Borated Water.

11.12.1 Southwest Research Institute (SwRI) under the direction of the Salem ISI Group performed ultrasonic examinations on two (2) welds. No recordable indications were noted.

Page 18 of 25

..

• FORM NIS.OWNER'S DATA REPORT.FOR I.RVICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101

2. Plant: Salem Generating station P.O. Box E Hancock's Bridge, N.J. 08038

3. Plant: Unit 2

4. owner's certificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

11. Examination summary (continued):

11.12.2 Quarterly chemistry samples were taken by the PSE&G Chemistry Department and the results were transmitted to.the Salem ISI Group per the Chemistry procedure. During the past 18 months, this program identified a few nonconformances. The nonconforming pipe was flushed and a new sample taken to verify it met the acceptance criteria.

11.13 Technical Specification 4.4.11.1 Reactor Coolant Pump Flywheel Examination (USNRC Regulatory Guide 1.14, "Reactor Coolant Pump Flywheel Integrity")

11.13.1 Summary Southwest Research Institute (SwRI) performed examinations on Reactor Coolant Pump (RCP)

Flywheels. Flywheels are tracked by their serial #

and original pump location, however, many have been moved into different pumps. The exam results are as follows:.

A. Performed "UT" examination of the top side of serial # 1-S-76P-917 which was originally installed in # 21 pump and is now installed in

1. 23 pump. Exam performed in-place.

B. Performed "PT", "MT", and "UT" examinations on serial # 1-S-88P-318 which was originally installed in # 24 pump and is now installed in

1. 22 pump. Exam performed with flywheel removed.

c. Performed "UT" examination of the top side of serial # l-S-0003 which was originally a spare flywheel and now is installed in # 21 pump. Exam 1 installed in-place. '

D. Performed "PT", "MT" and "UT" examinations on spare flywheel, serial I 2-S-75P-790. Flywheel was removed and examined at Westinghouse facility in Cheswick, Pa. Exam was performed using a Unit

1. 1 procedure because flywheel was originally installed in a Unit 1 pump.

Page 19 of 25

FORM NIS-9oWNER'S DATA REPORT FOR I~RVICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101

2. Plant: Salem Generating Station P.O. Box E Hancock's Bridge, N.J. 08038

3. Plant: Unit 2

4. owner's Certificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

11. Examination Summary (continued):

11.13.2 Results A. UT examination of flywheel, serial #'s 1S-88P-318, revealed a Code allowable laminar indication which was documented on CNF 3. This indication was accepted use "As-Is" by PSE&G.

B. UT examination on s:pare flywheel, serial 2S-75P-790, revealed a Code allowable indication which is documented on CNF 7. This indication was accepted use "As-Is" by PSE&G personnel.

11.14 NRC Bulletin 87-01 "Thinning of Pipe Walls in Nuclear Power Plants.

11.14.1 Summary Southwest Research Institute (SwRI) under the direction of the Salem ISI Group performed ultrasonic thickness measurements on eighty seven (87) piping components as identified by PSE&G engineering.

11.14. 2 Results Any area's identified having a wall thickness below minimum wall were submitted to PSE&G Engineering Department for disposition.

11.15 NRC Bulletin 82-02 "Degradation of Threaded Fasteners in the

.Reactor Coolant Pressure Boundary of Power Plants 11.15.1 Summary Visual (VT) and Magnetic Particle {MT) exams were performed on the primary manway bolts for all four (4) steam Generators. In addition, a VT exam was performed on all four (4) Reactor Coolant Pumps main flange bolting.

Page 20 of 25

FORM NIS--OWNER'S DATA REPORT FOR I.RVICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas co., 80 Park Plaza Newark, N.J. 07101

2. Plant: Salem Generating station P.O. Box E Hancock's Bridge, N.J. 08038

3. Plant: Unit 2

4. owner's Certificate of Authorization (if required} N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

11. Examination Summary (continued}:

11.15. 2 Results Two (2) bolts on # 21 Steam Generator hot leg and one (1) bolt on # 23 Steam Generator hot leg had minor indications observed during the visual examinations. Deficiency Reports and Code Job Packages were prepared to replace these bolts in kind. There were no discrepancies noted on the Reactor Coolant Pump flange bolting.

11.16 NRC Bulletin 88-08 "Thermal Stresses in Piping Connected to Reactor Coolant Systems 11.16.1 Southwest Research Institute (SwRI), under the direction of the Salem ISI Group, performed augmented ultrasonic and dye penetrant examinations on sixteen (16) 1.5 11 Safety Injection welds, two (2) 2 11 and five (5) 3 11 Chemical and Volume Control System welds for the third consecutive outage. No discrepancies were noted.

11.17 NRC Bulletin 88-11 "Pressurizer Surge Line Thermal Stratification.

11.17.1 Summary The Salem ISI Group performed visual examinations on all the existing surge line pipe supports/HEBA restraints and any insulation damage. A total of nine (9) supports were examined.

11.17.2 Results One restraint was found to have missing shims. A Deficiency Report was generated and dispositioned that the shims were not required and were removed during hot functional testing. The support drawing will be revised to reflect the "As-Built" condition.

Two (2) spring supports had minor deficiencies (misaligned and loose lock nut) which were corrected with work orders. No other discrepancies were noted.

Page 21 of 25

FORM NIS~WNER'S DATA REPORT FOR IieRVICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101

2. Plant: Salem Generating station P.O. Box E Hancock's Bridge, N.J. 08038

3. Plant: Unit 2 4 *. owner's Certificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

11. Examination summary (continued):

11.18 NUREG 0578 - "TMI" Lessons Learned - Performing Service Leak Exams, measuring leakage outside Containment, and take corrective actions necessary to reduce leakage as low as possible on systems likely to contain radioactive liquids in the event of an accident.

11.18.l Summary A. The Salem ISI Group performed service pressure leak exams on the Safety Injection, Chemical and Volume Control, Residual Heat Removal and Containment Spray Systems.

B. The PSE&G Research Corp., under the direction of the Salem ISI Group conducted the Waste Gas System Leak Test in accordance with Site Services procedure SC.SS-IS.WG-0003(R).

11.18.2 Results There were no adverse findings in the examinations or tests conducted relative to this bulletin.

11.19 Field Directive, S-C-R700-MFD-288, "Leak Rate Test Program for the Steam Generator Blowdown Isolation Valve (GB4) 11.19.l PSE&G Research and Test Lab under the field supervision of the Salem ISI Group, conducted leak rate tests on all four (4) Steam Generator Blowdown Valves (GB-4's) in accordance with Site Service procedure 11.19.2 Results*

All four valves had acceptable leak rates below the test acceptance criteria of s 30,000 seem. No discrepancies were noted.

Page 22 of 25

FORM NIS--JWNER'S DATA REPORT FOR !~VICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101

2. Plant: Salem Generating station P.O. Box E Hancock's Bridge, N.J. 08038

3. Plant: Unit 2

4. Owner's Certificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

11. Examination summary (continued):

11.20 Field Directive, S-C-N510-NFD-0361-1, "Testing of Valves Discharging Waste Gas Decay Tank Contents to the Environmentn.

11.20.1 Summary PSE&G Research and Test Lab under the field supervision of the Salem ISI Group conducted leak rate tests on four (4) Waste Gas Decay Tanks, two (2) Waste Gas Compressors and the Waste Gas Header.

11. 20. 2 Results The Waste Gas Decay Tanks and the Waste Gas Compressors had acceptable leakage rates per the acceptance criteria in the procedure (0 leakage).

The leak rate test on the 2WG41 valve had a leakage in excess of the acceptance criteria of 1,850 seem.

Deficiency Report (DR) SMD-92-668 was dispositioned to rework the valve and retest.

Page 23 of 25

FORM NIS.OWNER'S DATA REPORT FOR ~RVICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES

1. Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101

2. Plant: Salem Generating Station P.O. Box E Hancock's Bridge, N.J. 08038

3. Plant: Unit 2

4. Owner's Certificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

12. owner's Report for Repairs or Replacements, Forms NIS-2 and/or NR-1.

12.1 In accordance with the requirements of the later editions of the Code, completed Owner's Report for Repairs or Replacements, Forms NIS-2, are submitted as an attachment to this report.

12.2 In addition, in accordance with Relief Request NLR-N87232-2 approved by letter dated May 16, 1989 from the USNRC to Mr.

Steven E. Miltenberger, in lieu of form NIS-2, National Board Form NR-1 are also submitted as an attachment to this r~port.

NOTE: A reference index has been prepared and is also included with this attachment.

Page 24 of 25

FORM NIS-~WNER'S DATA REPORT FOR Ii9RVICE INSPECTORS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza Newark, N.J. 07101

2. Plant: Salem Generating Station P.O. Box E Hancock's Bridge, N.J. 08038

3. Plant: Unit 2

4. Owner's Certificate of Authorization (if required) N/A.

5. Commercial Service Date: 10/13/81

6. National Board Number for Unit: N/A

7. Examination Dates: 06/25/90 through 5/10/92

12. Owner's Report for Repairs or Replacements, Forms NIS-2 and/or NR-1.

We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code,Section XI.

Date

- __1~/-'2;. . . .i. 1__ , 19 '[z_ Signed PSE&G owner by ~ E~c&~

Tl Certificate of Authorization No. (if applicable) 4tf Expiration date CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of New Jersey and employed by Arkwright Mutual Insurance Company, Norwood, Massachusetts, have inspected the components described in this owner's Report during the period 6/25/90 to 5/10/92 and state that to the best of my knowledge and belief the Owner has performed examinations and taken corrective measures described in this owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this owner's Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Date __1_-2-_1--_*_, 19 ~

Factory Mutual System

_ ____.:~~~~(::;..._-*~(;~*d?.L.:..:L=--

Ins Commissions N_r-J' 73 "x .,

National Board, state, Province and No.

Page 25 of 25

• Index of NIS-2 and NR-1 ~~s I. NIS-2 Forms

• Component 21SJ29 22SJ29 21SJ48 24SJ29 Work Order 931023009 931010003 931006022 911103057 Brief Description

• Rebuilt valve, installed new disk assembly Rebuilt valve, replace disk assembly Repaired valve Replaced with new valve 2CV115 910601207 Replaced valve cap and plug 2PR3 950406003 Removed valve tested and reinstalled 2PR4 950406001 Removed valve tested and reinstalled 2PR5 950406002 Removed valve tested and reinstalled II. NR-1 Forms Code Job # Brief Description P90-050 Modify supports 2-AFS-167 and 2-AFA-166 P91-024 Modif ication/changeout of Service Water Piping Supports P91-025 Modif ication/changeout of Service Water Piping Supports P91-028 Modif ication/changeout of Service Water Piping Supports P91-029 Modif ication/changeout of Service Water Piping Supports P91-054 Relocated and upgraded valve 21GB3 and modified supports 2P-BDA-179 and 2C-BDA-31 P91-055 Relocated and upgraded valve 22GB3 and modified support 2C-BDS-60A

• P91...;.056 P91-057 P91-090 Relocated and upgraded valve 23GB3 and modified support 2-SG-BLS-35 Relocated and upgraded valve 24GB3 and modified support 2P-BDA-183 Modified eleven (11) Emergency Core Cooling System Supports S88-231 Replaced cage, plug, pin assembly and seat ring on 23MS10 valve S88-243 Replaced valves 24BF57 and 24BF58 S89-19 Weld repair to gasket seating surface on valve 24MS7 S90-047 Replaced stem and plug assembly on valve 21MS169 S90-049 Replaced stem and plug assembly on valve 23MS169 S90-050 Replaced valve seat assembly on valve 24MS169 S90-053 Replaced stem and plug assembly on valve 23MS171 S90-055 Replaced waterbox cover bolts on C.F.C.U. # 2SWE32 S90-095 Replaced snubber 2C-PRSN-30 (serial # 338) with snubber (serial # 25750)

S90-096 Replaced snubber 2P-SISN-102A (serial # 340) with snubber (serial # 24747)

S90-102 Replaced plug, stem, pin and cage assembly on valve 2PR1 S90-105 Replaced eight (8) bonnet studs and nuts on valve

• 2CV122 S90-106 Replaced valve 23MS15 in kind with valve (serial no .

N55100-03-0065)

S90-108 .Replaced valve 24MS15 with valve SN N55100-03-064 S90-110 Replaced snubber 2C-PRSN-39 (serial # 17045) with snubber (serial # 17817)

.. .

~

S90-117 a.aced plug and stem on va& 2SS49 S90-118 Replaced bonnet, cage, stem and plug and pin assembly on valve 2CV131 S90-122 Replaced snubber 2S24-FWSN-13A (serial # 481) with snubber (serial # 27722)

S90-123 Replaced snubber 2S22-FWSN-13A (serial # 489) with snubber (serial # 27824)

S90-126 Replaced snubber 2A-MSASN-156 (serial # 20240) with snubber (serial # 14247)

S90-127 Replaced snubber 2C-PRSN-405A (serial # 644) with snubber (serial # 17809)

• S90-128 Replaced snubber 2C-PRSN-401 (serial # 625) with snubber (serial # 17833)

S90-129 Replaced snubber 2C-PRSN-405 (serial # 602) with snubber (serial # 17811)

S90-146 Replaced stem, plug, cage assembly and made weld repair to seat ring gasket surface on valve 24MS10 S90-151 Replaced one bolt (lC-12) on # 21 Steam Generator primary manway S90-152 Replaced one bolt (3H-15) on # 23 Steam Generator primary manway S90-153 Replaced one bolt (4H-10) on # 24 Steam Generator primary manway S90-154 Replaced damaged bolt # 13 on # 23 Steam Generator secondary manway S90-155 Replaced eight (8) studs and nuts in kind on valve 2SJ31 .

S90-158 Replaced # 23 Steam Generator inboard secondary manway bolt #'s 3, 7, 9, 11, 14, 17 and outboard secondary manway bolt # 19 S90-159 Replaced 3 (3) bolts in # 23 Steam Generator handhole cover S90-174 Replaced stem, disc, and key assembly in kind on valve 2SJ6 S90-198 Replaced lost bolt in # 21 Steam Generator handhole cover S90-204 Made weld repair to body and bonnet gasket seating surfaces on valve 22GB3 S90-216 Replaced studs and nuts in kind on flow orifice #

2FE641B S90-222 Replaced safety relief valve 2CV253 S91-101 Replaced valve 2VC5 in kind .

S91-223 Replaced # 22 BAT pump with spare pump S91-254 Replaced twelve (12) cover studs and nuts on valve 23SJ156 S91-296 Replaced # 21 Boric acid Transfer Pump S91-318 Replaced eight (8) studs and sixteen (16) nuts on # 22 Charging Pump discha~ge flange S91-340 Replaced vent line and modified supports on 24MS167 valve after valve maintenance s91.;.341 Replaced vent line on 23MS167 valve after valve maintenance S91-342 Replaced vent line on 22MS167 valve after valve maintenance S91-343 Replaced vent line on 21MS167 valve after valve maintenance .

S91-345 Replaced plug and stem assembly on valve 24MS169 /

S91-347 Replaced valve seat, stem and plug assembly on valve 22MS169 .

.* .

I.;

S91-348 Rlaced valve seat, stem an~ug assembly on valve 2 169 S91-349 Replaced stem and plug assembly on valve 24MS171 S91-351 Replaced valve seat, stem and plug assembly on valve 22MS171 S91...;.364 Replaced valve plug, stem and seat ring assembly on -

valve 22GB4 S91-366 Replaced valve plug, stem and seat ring assembly on valve 23GB4 S91-370 Replaced stem, plug, pin and cage on valve 2PS3 S91-375 Replaced mechanical snubber (serial # 18206) with snubber (serial # 27631)

S91-378 Replaced valve 22SJ138 with different design type S91-379 Replaced two (2) primary manway bolts on # 21 Steam Generator S91-380 Replaced one (1) primary manway bolts on # 23 steam Generator S91-385 Replaced valve bonnet and bolting on valve 2CV181 S91-386 Replaced mechanical snubber (serial # 629) with snubber (serial # 17698) .

S91-390 Replaced bolting on valve 2CV4 S91-393 Performed weld repair on body of valve 25SW72 S91-394 Replaced valve 21SJ48 with valve (SN N69971-0l-OOO).

S92-002 Performed weld repair on disc for valve 2CV5 S92-003 Replaced mechanical.snubber (serial# 354) with snubber (serial # 12912)

• S92-004 Replaced mechanical snubber (serial # 352) with snubber (serial # 12099) 592-016 Replaced mechanical snubber (serial # 13396) with snubber (serial # 20239)

S92-046 Replaced valve 24SJ29 with serial # N69959-00-0006 S92-055 Replaced outlet disc on valve 22MS167 S92-062 Replaced valve plug assembly on valve 2PR1 S92-067 Machined # 21 Steam Generator secondary side outboard hand hole seating surf ace S92-068 Machined # 21 Steam Generator secondary side inboard hand hole seating surf ace *.

S92-080 Replace inlet and outlet disc in valve 21MS167 S92-081 Replace outlet disc in valve 23MS167 S92-082 Replaced cylinder (bonnet) stud on valve 24MS161 S92-087 Performed weld repair on valve body seat, disc and replaced bolting for valve 21BF22 S92-088 Replaced mechanical snubber (serial # 38312) with snubber (serial # 92612571)

S92-089~* . Performed weld repair on valve 23BF22 and replaced bolting S92-090 Performed weld build-up on valve seat and valve body and replaced bolting on valve 22BF22 S92-091 Performed weld build-up on valve seat and valve body and replaced bolting on valve 24BF22 S92-094 Replaced plug and stem assembly on valve 2CV55 592-170 Inspected, cleaned and installed new diaphragm on valve 22CV156 592-180 Replaced cage, stem, plug assembly and bolting on valve 2PS1 592-201 Replaced bolting with upgraded SA-564 Grade 630 I material on valve 22SJ43 S92-251 Replaced valve 22SJ48 with serial # 53526 S92-293 Replaced stud and nut on check valve 21MS46