ML18089A427
| ML18089A427 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/20/1983 |
| From: | Liden E Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18089A428 | List: |
| References | |
| NUDOCS 8310280119 | |
| Download: ML18089A427 (18) | |
Text
'*
OPS~G*
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department October 20, 1983 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014 Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch 1 Division of Licensing Gentlemen:
IN-SERVICE INSPECTION REPORT FACILITY OPERATING LICENSE DPR-75 NO. 2 UNIT SALEM GENERATING STATION DOCKET NO. 50-311 This report is being submitted in accordance with Article IWA-6220(b),Section XI of the ASME Boiler and Pressure Vessel Code and the U. s. Nuclear Regulatory Commission Technical Specifications issued to Public Service Electric and Gas Com-pany for Salem Unit No. 2.
A copy is being forwarded to the New Jersey Department of Labor and Industry under separate cover.
The submittal is composed of Form NIS-1 "Owners Data Report for In-Service Inspection" and Volume I and II of the 111983 In-Service Examination of Selected Components at Salem Generating Station, Unit No. 2 11, prepared for PSE&G by Southwest Research Institute.
Field data to support this report is on file at the plant site.
If additional information is required, please do not hesitate to contact us.
Enclosure The Energy People Very truly yours,
./f4 /
~*
/c,,t&~~
L
.d I
E. A. Ll en Manager -
Nuclear Licensing and Regulation
'/ ~"""'"'"'""
r----
Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission CC:
Mr. Donald C. Fischer (w/o Enclosure)
Licensing Project Manager Mr. James Linville (w/o Enclosure)
Senior Resident Inspector 10/20/83
I FORM NIS-1 OWNERS'S DATA REPORT FOR INSERVICE INSPECTIONS 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 Statiori P.O. Box E, Hancock's Bridge, N.J.
08038
- 3.
Plant Unit 2
- 4.
Owner Certificate of Authorization (if required) N/A.
- 5.
Commercial Service Date 10/13/81.
- 6.
National Board Number for Unit N/A.
- 7.
Examinations Dates:
1/22/83 through 7/31/83.
- 8.
This examination report is for the first examination conducted in the first inspection period which ends
- 10/91.
Salems first inspection interval is from 10/81
-to 7/83.
- 9.
Component Inspected:
MANUFACTURER STATION OR COMPONENTS OR MANUFACTURER OR INSTALLER PROVINCE NATIONAL APPURTENANCE OR INSTALLER SER. NO.
NUMBER BOARD NO.
- 2 Reactor Vessel
- 24 Steam Generator Combustion Engineering Westinghouse Tampa Div.
P.O. Box 19218 Tampa, FL 33616 II II II II II II FORM NIS-1 OWNERS'S DATA REPORT FOR INSERVICE INSPECTIONS 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 Certificate of Authorization (if required) N/A.
- 5.
Commercial Service Date 10/13/81.
- 6.
National Board Number for Unit N/A.
- 7.
Examinations Dates:
1/22/83 through 7/31/83.
- 8.
This examination report is for the first examination conducted in the first inspection period which ends 10/91.
Salems first inspection interval is from 10/81 to 7/83.
- 9.
Component Inspected:
COMPONENTS OR MANUFACTURER APPURTENANCE OR INSTALLER
NUMBER BOARD NO.
NOTE:
This report also contains augmented examinations required by Salem Technical Specification and Regulatory Guid~s, circulars and bulletins issued by the United States Nuclear.Regulatory Commission.
Chemical United N/A N/A N/A Volume &
Engineers &
Control Constructors Piping 30 s. 17th St.
System Philadelphia, PA 19101 Containment UE&C N/A N/A N/A Spray Piping System Main Steam UE&C N/A N/A N/A Piping System FORM NIS-1 OWNERS'S DATA REPORT FOR INSERVICE INSPECTIONS 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 Certificate of Authorization (if required) N/A.
- 5.
Commercial Service Date 10/13/81.
- 6.
National Board Number for Unit N/A.
- 7.
Examinations Dates:
1/22/83 through 7/31/83.
- 8.
This examination report is for the first examination conducted in the first inspection period which ends 10/91.
Salems first inspection interval is from 10/81 to 7/83.
- 9.
Component Inspected:
MANUFACTURER STATION OR COMPONENTS OR MANUFACTURER OR INSTALLER PROVINCE NATIONAL APPURTENANCE OR INSTALLER SER. NO.
NUMBER BOARD NO.
Pressurizer UE&C N/A N/A N/A Relief Piping Sys.
Reactor UE&C N/A N/A N/A Coolant Piping Sys.
Residual Heat UE&C N/A N/A N/A Removal Piping Sys.
Steam Gen.
UE&C N/A N/A N/A Feed Piping System Safety UE&C N/A N/A N/A Injection Piping Sys. -
FORM NIS-1 OWNERS'S DATA REPORT FOR INSERVICE INSPECTIONS 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 Certificate of Authorization (if required) N/A.
- 5.
Commercial Service Date 10/13/81.
- 6.
National Board Number for Unit N/A.
lOo EXAMINATIONS:
Examinations were conducted by PSE&G as well as companies under contract to PSE&G.
Attached you will find copies of each contractor report which are part of this report.
The following is a brief summary with further details found in the attached reports and on file at Salem Generating Station.
Since nearly all inservice examination requirements can be found in Salem's Technical Specifications, this summary is arranged according to Technical Specifications paragraph number followed by applicable N.R.C. circulars and bulletins.
1.0 Technical Specification 4.0.5 -
ASME Section XI The examinations conducted during this outage completed the required number of examinations for our first examination conducted in the first inspection period of the ten year long-term In-Service Inspection Plan.
1.1 South West Research Institute (SWRI) -
conducted 174 Ultrasonic 94 Liquid Penetrant, 21 Magnetic Particle and 43 Visual Examinations.
The examinations were conducted on selected welds and the main steam, Residual Heat Removal, Reactor Coolant, including Reactor Vessel Examination by use of the PAR Device, Chemical Volume Control, Steam Generator Feedwater, Safety Injection and Containment Spray Systems.
There were nine (9) nonconformances reported by SWRI:
During the VT examination indications were observed on four examination areas:
valve 2 PS 29, Steam Generator manway bolting, valve 2 CV2, and No. 21 Reactor Coolant Pump lugs.
These indications were reported on Customer Notification Forms (CNFs) SAL003, SAL007, FORM NIS-1 OWNERS'S DATA REPORT FOR INSERVICE INSPECTIONS 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 Certificate of Authorization (if required) N/A.
- 5.
Commercial Service Date 10/13/81.
- 6.
National Board Number for Unit N/A.
- 1. 1 * ( cont. )
SAL008, and SAL009, respectively.
The indications on CNFs SAL007 and SAL009 were accepted "as is" after evaluation and the CNFs were closed.
The indication on CNF SAL008 was accepted "as is" with the stipulation that the va~ve bolting be replaced during the next refueling outage and the CNF was closed.
The loose nut on CNF SAL003 was tightened by PSE&G personnel and the CNF was closed.
Liner indications were observed during the PT examinations of weld Nos.
2-RC-1232-18 and 2-RC-1222-7 and reported to PSE&G on CNFs SALOOl and SAL002, respectively.
Both indications were removed by light hand filing and the CNF's were closed.
The 10-year examination, as required by U.S.
NRC Regulatory Guide 1.14, Article C, was performed on No. 22 Reactor Coolant Pump Flywheel.
Linear indications were observed during the PT examinations of Keyways A, B, and C and reported-to PSE&G on CNFs SAL004 and SAL005.
Exploratory grinding was performed and the indications were accepted after evaluation by PSE&G.
No reportable indications were observed during the MT or the UT examinations of the Reactor Coolant Pump Flywheel.
1.2 Catalytic Inc. Q.C. Group conducted visual examination on 81 Nuclear Class I, 39 Nuclear Class II, 217 Class III several discrepancies were found, i.e. debris, loose bolts, rust etc. which were corrected by work orders.
1.3 PSE&G Maintenance Department conducted 29 safety/relief valve lift set tests, including all main steam safety and various system relief valves.
FORM NIS-1 OWNERS'S DATA REPORT FOR INSERVICE INSPECTIONS 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 Certificate of Authorization (if required) N/A.
- 5.
Commercial Service Date 10/13/81.
- 6.
National Board Number for Unit N/A.
2.0 Technical Specification 4.4.6.0 -
Steam Generator Tube Eddy Current Inspection.
Through full length 2.1 Eddy Current Examinations were conducted on 21-24 Steam Generators this outage.
The examinations were conducted by Westinghouse Electric Corporation and coordinated by the Salem ISI Group.
2.2 This outage 100% of the tubes in each generator were examined.
PSE&G elected to do 100% due to the indications found in Unit I and to re-establish a baseline using the up to date multi-frequency techniques.
The results of the Examination are as follows:
- 21 HOT/COLD 3388 TUBES PROBED
- 22 HOT/COLD 3388
- 23 HOT/COLD 3387*
- 24 HOT/COLD 3388
- One Tube was shop plugged
% OF INDICATIONS T.S. Classi-
- 21 f ication
<20% Imper-0 fection
> 20%-30% De-0 graded
> 40% Defective 0
- Unable to assign a pertentage due to location in apex.
- 22 11 11 11
- l #23
- 24 11 3
8 0
0 0
I FORM NIS-1 OWNERS'S DATA REPORT FOR INSERVICE INSPECTIONS 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 Certificate of Authorization (if required) N/A.
- 5.
Commercial Service Date 10/13/81.
- 6.
National Board Number for Unit N/A.
From the results, no (0) tubes were plugged in 21, 23, 24 Steam Generators and two(2) were plugged in 22 Steam Generator.
At this time the total number of tubes plugged in Salem Unit I Generators are:
GEN.
- 21
- 22
- 23
- 24 No Tubes Plugged 0
2 1 (shop 0
plug) 3.0 Technical Specification 4.4.11.1 Reactor Coolant Pump Flywheel Examination.
3.1 Summary A ten* year examination as required by Reg.
Guide 1.14 Article C was performed on 22 RCP motor flywheel (flywheel was removed from motor).
Linear indications were found by the liquid penetrant method on keyways A, B, & C and reported on customer notification forms.
Exploratory grinding was performed and found acceptable by PSE&G and Westinghouse after evaluation.
No reportable indications were found during the magnetic particle and ultrasonic portions of the examination.
Also, 21 RCP motor flywheel was tested in place (top surface only) using ultrasonic and magnetic particle methods.
No recordable indications were found.
4.0 Technical Specification 4.4.10.1.2 Surveillance of Reactor Vessel Irradiated Specimen.
4.1 Summary FORM NIS-1 OWNERS'S DATA REPORT FOR INSERVICE INSPECTIONS 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 Certificate of Authorization (if required) N/A.
- 5.
Commercial Service Date 10/13/81.
- 6.
National Board Number for Unit N/A.
4.1 (cont.)
Capsule "T" was removed from Unit II Reactor Vessel this outage and placed in the spent fuel pit.
This capsule will be transmitted to Westinghouse for analysis.
5.0 Technical Specification 4.6.l.2d -
Containment Type B & C Leak Rate Testing.
5.1 PSE&G Research Corporation under field supervision of the ISI Group conducted Type "C" test on 117 containment isolation valves and Type "B" test on 145 mechanical and electrical containment penetrations.
Prior to this outage a leak rate of 23753 seem was recorded.
The present leakage is 17,635 seem.
6.0 Technical Specification 4.6.1.3.b - el 100' and 130' airlock leak rate test.
6.1 The Airlock Tests were conducted by PSE&G research corporation under field direction of the MIET group.
The combined leakage of the Airlocks is 2134 seem.
7.0 Technical Specification 4.6.1.6.1 Visual Inspection of Containment Surfaces.
7.1 Summary PSE&G Research Corp along with the Salem ISI Group performed a containment liner inspection both prior to and after the Reactor Containment Type "A" test.
No Adverse conditions were noted.
8.0 Technical Specification 4.7.9.a Visual* Inspection of all Hydraulic and Mechanical Snubbers.
8.1 Summary Catalytic Inc. QC Department with assistance from the Salem ISI Group conducted visual examinations on all mechanical snubbers.
FORM NIS-1 OWNERits DATA REPORT FOR INSERVIcttINSPECTIONS 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.-0. Box E, Hancock's Bridge, N.J.
08038
- 3.
Plant Unit 2
- 4.
Owner Certificate of Authorization (if required) N/A.
- 5.
Commercial Service Date 10/13/81.
- 6.
National Board Number for Unit N/A.
8.1 Summary (cont.)
No discrepencies were found that would effect operability however, several were found with minor rust (Attachment No.s) missing washers etc.
Work orders have been issued on these.
The PSE&G Maintenance Department conducted visual examinations on all hydrulic snubbers.
Several discrepencies were noted such as union leaks and a hanger on reser-voir line not secured.
These discrepencies were corrected by Catalytic Inc. under the direction of the PSE&G NCS Group.
9.0 Technical Specification 4.7.9.c Functional Testing of Selected Hydraulic and Mechanical Snubbers.
9.1 Summary -
Hydraulic Technical Specification 3/4.7.9 requires functional testing on 10% of the snubber total during each plant refueling outage.
Accordingly, two hydraulic snubbers were tested at Wyle Laboratories, Huntsville, Alabama.
Neither snubber met the "lock-up" nor "bleed-rate" velocity requirements.
The test results and failure mode of these two snubbers were exactly the same as those of Salem No. l snubbers.
Further, based on the lesson learned from Salem No. 1, it was concluded that the remaining fourteen snubbers would not meet the specification requirements and their "as received" tests were not worthy to perform.
The NRC con-curred with this approach and indicated to test 25% of the total number of the snubbers (four (4) snubbers) to verify the consistency of the test results.
Accordingly, a total of six snubbers (including special tests on two snubbers, as described in the report) were tested in "as ~eceived" condition and the remaining ten units were disassembled without performing the test.
FORM NIS-1 OWNERS'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES
- 1.
Owner:
Pl!_blic 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 Certificate of Authorization (if required) N/A.
- 5.
Commercial Service Date 10/13/81.
- 6.
National Board Number for Unit N/A.
9.1 Summary -
Hydraulic (cont.)
All sixteen snubbers were retested satisfactorily.
performed on the "Rod Eye No. 32, because of damage problems.
refurbished and Weld repair was Tube" of snubber due to disassembly One 200 KIP main steam isolation valve
.snubber was also functionally tested and found acceptable.
9.2 Summary -
Mechanical As per Technical Specification 4.7.9c 10% of the mechanical snubbers were sent to Wyle Laboratories for Functional Testing.
The results from the first 10% revealed one (1) PSA 1/2 failed.
Due to this failure and additional 10% were sent for testing.
On the second (2nd) sample one (1) PSA -
1/4 failed, another 10% were pulled.
On the third (3rd) two (2) PSA -
1/4 were found unacceptable.
At this time it was obvious,that all PSA 1/4 and PSA 1/2 were in question because all tests on larger bore snubbers were satisfactory.
The ISI Group proposed the 4th sample be the remainder of the PSA 1/4 -
All PSA 1/2 were tested.
The NRC concurred with this approach but suggested we select one (1) each of the larger sizes also.
The fourth (4th) sample results were five (5) of the ten (10) PSA -
1/4 failed and all larger sizes were satisfactory.
FORM AS NIS-1 OWNER'S DATA REPORT REQUIRED BY THE PROVISIONS FOR INSERVI.INSPECTIONS 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 Certificate of Authorization (if required) N/A.
- 5.
Commercial Service Date 10/13/81.
- 6.
National Board Number for Unit N/A.
9.2 Summary -
Mechanical All failed snubbers were sent to their manufacturer, Pacific Scientific, Anaheim, California, for retest, repair and evaluation.
Seven (7) units were repaired and retested satisfactorily.
Two (2) units, Sr. No. 11525, 2A-MSA-SN-157 and Sr. No.
6472, 2C-SISN-14 were scrapped, being beyond economical repair and were replaced with new snubbers.
PSE&G Engineering also performed a safety evaluation on the failed snubbers, and it was concluded that the attached piping and components were not impaired due to inoperability of the snubbers.
10.0 NRC Circular 76-06 and NRC bulletin 79-17 commitment to examine and/or flush stainless steel lines containing stagnent borated water.
10.1 Summary As part of the !SI program, SWRI performed ultrasonic examinations on twelve(l2) piping welds covered by this circular.
Quarterly chemistry samples were taken by the PSE&G Chemistry Department and results transmitted to the Salem ISI Group as required by Maintenance Procedure Ml7G.
There were no adverse findings in the examinations or tests conducted relative to the reporting requirement of this circular.
11.0 NuReg 0578 -
TMI Lessons Learned -
Performing Service Pressure 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 incident.
RM AS NIS-1 OWNER'S DATA REPORT REQUIRED BY THE PROVISIONS FOR INSERVI.INSPECTIONS 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 Certificate of Authorization (if required) N/A.
- 5.
Commercial Service Date 10/13/81.
- 6.
National Board Number for Unit N/A.
11.1 Summary The Salem ISI Group along with members of the PSE&G Maintenance Department performed Service Pressure Leak Exams ori the Safety Injection, Chemical Volume and Control, Residual Heat Removal and Containment Spray Systems.
In addition, PSE&G Research Corp. under the direction of the Salem ISI Group conducted the Waste Gas System Leak Rate Test in accordance with Maintenance Procedure Mlle.
There were no adverse findings in the examinations or tests conducted relative to this bulletin.
12.0 NRC Bulletin 79-13 Steam Generator Feedwater Nozzle Cracking, Follow-Up 12.1 Summary Magnaflux Quality Services under the direction of the Salem ISI Group performed Radiography on all four Steam Generator Nozzle to Piping Welds.
The radiographs were evaluated for any cracking, and were compared to radiographs taken previously.
The results of the examination were satisfactory.
13.0 NRC Bulletin 82-02 Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary of Power Plants.
13.1 Summary Due to this Bulletin, all Stearn Generator Primary Manway Bolts were Magnetic Partical and Visually examined by Southwest Research Institute under the direction of the Salem ISI Group.
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVIC,INSPECTIONS 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 Stati9n P.O. Box E, Hancock's Bridge, N.J.
08038
- 3.
Plant Unit 2
- 4.
Owner Certificate of Authorization (if required) N/A.
- 5.
Commercial Service Date 10/13/81.
- 6.
National Board Number for Unit N/A.
13.1 Summary (cont.)
One linear indication was observed during the MT examination of bolt No. 12 on 22-STG-IMB and reported to PSE&G on CNF SAL006.
The indication was reworked by PSE&G and reexamination by SwRI personnel revealed no recordable indications.
No other reportable indications were observed during the examinations.
Also the reactor coolant pump main flange bolts were visually examined in place by the PSE&G Maintenance Department and the ISI Group.
No Discrepancies were noted.
14.0 NRC Circular 76-06 and Bulletin 79-17 Commitment to Examine and/or Flush Stainless Steel Lines Containing Stagnant Borated Water.
14.1 As part of the In-service Inspection Program SwRI conducted ultrasonic examinations of 15 piping welds within the boundaries covered by this circular.
Also, the MIET group conducted service pressure leak examinations on the Safety Injection, Chemical Volume and Control, Residual Heat Removal, and Containment Spray Systems.
There were no adverse findings in any examination or test conducted relative to the reporting requirement of this circular.
14.2 Portions of Containment Spray, Safety Injection, and Chemical Volume Control systems were flushed (and continue to be flushed) during the monthly pump capacity surveillance testing as per Surveillance Procedure SP (O) 4.0.5-P.
Cloride sampling and testing for cloride content of those samples of fluids in stagnant piping was conducted on a quarterly basis.
During the past 12 months there were no nonconformances identified.
FORM NIS-1 OWNERS'S DATA REPORT FOR INSERVICE INSPECTIONS 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 Certificate of Authorization (if required) N/A.
- 5.
Commercial Service Date 10/13/81.
- 6.
National Board Number for Unit N/A.
15.0 Nuclear Reg. 0578 TMI Lessons Learned Report 15.1 As a result of the TMI accident, a commitment to the NRC requires on an annual basis a service pressure leak examination of systems likely to contain radioactive fluids outside the containment during an incident.
The commitment also requires a quantitative report of leakage and to reduce leakage as low as possible.
The systems requiring the leak examination are:
Containment Spray, Residual Heat Removal, Safety Injection, Chemical Volume and Control, Reactor Coolant Sampling, Waste Disposal Liquid, and Waste Disposal Gas.
There were no major problems with any of the systems and most of the leakage was corrected by tightening valve packing or mechanical joints.
15.2 The Maintenance Department under the direct field supervision of the ISI Group, conducted all of the Service Pressure Leak Examinations.
16.0 NRC Bulletin 79-13 Stearn Generator Nozzle Cracking Follow-up.
16.1 Magnaflux Quality Service under the direction of ISI Group performed Radiography on all four Stearn Generator Nozzle to Piping Welds.
The radiographs were evaluated for any cracking, and were compared to radiographs taken last outage.
The results of the examination were satisfactory.
17.0 NRC Bulletin 82-02 Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary of Power Plants 17.1 Due to this Bulletin, all Steam Generator Primary Manway Bolts were Magnetic Particle Tested and visually examined by SwRI under the direction of the ISI Group.
FORM NIS-1 OWNERS'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES
- 1.
Owner:
Pcrblic 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 Certificate of Authorization (if required) N/A.
- 5.
Commercial Service Date 10/13/81.
- 6.
National Board Number for Unit N/A.
17.1 Also, the Reactor Coolant Main Flange Bolts were visually inspected in place by the PSE&G Maintenance Department and the ISI Group for any abnormalties.
No adverse findings were found on any of the examinations.
FORM NIS-1 OWNERS'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES
- 1.
Owner:
Public Service Electric & Gas Co., 80 Park Plaza
- Newark, N.~.
07101.
- 2.
Plant.:
Salem Generating Station P.O. Box E, Hancock's Bridge, N.J.
08038
- 3.
Plant Unit 2
- 4.
Owner Certificate of Authorization (if required) N/A.
- 5.
Commercial Service Date 10/13/81.
- 6.
National Board Number for Unit N/A.
We certify that the statements made up in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code,Section XI.
Certificate of Authorization No. (if applicable)
N/A 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 Lumberman's Mutual Casualty Company, Long Grove, Illinois, have inspected the components described in this Owner's Data Report during the period 10/2/82 to 4/19/83 and state that to the best of my knowledge and belief the Owner has peiformed examinations and taken corrective measures described in this Owners' Data Report in accordance with the requirements of the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employee makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners' Data 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
, 19 Inspector's Signature Commissions National Board, State Province and No.