ML20235Y091
| ML20235Y091 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 10/16/1987 |
| From: | Tiernan J BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20235Y094 | List: |
| References | |
| NUDOCS 8710200216 | |
| Download: ML20235Y091 (9) | |
Text
{{#Wiki_filter:I g. 1 BALTIMORE GAS AND ELECTRIC CHARLES CENTER R O. BOX 1475 BALTIMORE, MARYLAND 21203 1 -t JOSEPH A.TIERNAN Vice PRESIDENT NUCLEAR ENEROY October 16, 1987 U. S. Nuclear Regulatory Commission Washington, D.C.- ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318 Inservice Inspection ReDorts ENCLOSURES: (1) ASME Boiler & Pressure Vessel Code Section XI, Form NIS-1 (2) 1987 Inservice Examination of Selected Class 1 and Class 2 Components and Systems, Volumes 1 through 9 (3) Steam Generator- #21 and
- 22 Eddy Current Testing Final Report, March / April 1987 Gentlemen:
Please find enclosed the Inservice Inspection reports for Calvert Cliffs Unit.2. The results are incorporated within the three enclosures submitted. These inspections. fulfilled the intentions-and requirements stated in our examination plan and our commit-I ment to comply with ASME Code Section XI Inservice Inspection requirements. Should you have any questions on the contents of this report, please do not hesitate to contact us. L I Very truly yours, l JAT/LMD/gla l Enclosures g \\ \\ 8710200216 871016 PDR ADOCK 05000318 [ G PDR
U. S.. Nuclear Regulatory Commission
- October 16, 1987
.i Page 2' l j i cc:. 'D. A..Brune, Esquire J. E. Silberg, Esquire R. A. Capra, NRC S. A.-McNeil,.NRC q W. T. Russell,.NRC T. Foley/D.C. Trimble,'NRC i l l l. l l 1
i r h ENCLOSURE'(1) l 1 TO BALTIMORE. GAS AND ELECTRIC COMPANY'S INSERVICE INSPECTION REPORT. FOR CALVERT CLIFFS UNIT 2 ASME BOILER AND PRESSURE VESSEL CODE SECTION XI, FORM NIS-1 l i l l l l
DATEi-Sectember 28, 1987 NIS-1 PAGE 1 of 6 NIS-1 FORM NIS-1 OWNER'S DATA-REPORT FOR INSERVICE INSPECTIONS (As Required by the Provisions of the ASME Code' Rules)
- 1. Owner:
Baltimore Gas and Electric Company P. 0. Box 1475 Baltimore, MD 21203 2. Plant: Calvert Cliffs Nuclear Power Plant Lusby Post Office Lusby,.MD 20657 3. Plant Unit: 4. Owner Certification of Authorization: l .#13. NA
- 5. Commercial Service Date:
6. National Board Number for Unit: Acril 1, 1977 20912_ 7. Components Inspected: ) i COMPONEl'T MANUFACTURER MANUFACTURER STATE NATIONAL OR OR OR INSTALLER OR BOARD 1 APPURTENANCE INSTALLER SERIAL # PROVINCE i NUMBER Reactor Combustion Pressure Engineering CE-67108 1400lNV 20912 s Vessel Reactor Combustion Pressure Engineering CE-67208 1400lNV 20912 Vessel Closure Head Steam combustion Generator Engineering CE-67505 1400lNV 20925
- 21
) Steam Combustion i Generator Engineering .CE-67507 14001NV 20924
- 22 Reactor Combustion Coolant Engineering CONTRACT No.
Pipe 72467
- 22B Reactor Byron Jackson l
Coolant Pump SN-0444 1400lNV 68-1-N-0444 ~ I . J
s DATES. Seotember 28, 1987 NIS
- PAGE - 2 of 6
NIS-1 7. Components Inspected (Continued): i-I. COMPONENT MANUFACTURER MANUFACTURER STATE NATIONAL OR OR OR INSTAT.TRR OR BOARD-I APPURTENANCE
- INSTAT.TRR SERIAL #
PROVINCE # NUMBER
- 21A RCP Westinghouse SN-4S-77P108 Motor (Motor)
Flywheel )
- 21B RCP Westinghouse SN-4S-79P528 Motor (Motor)
Flywheel
- 22A RCP Westinghouse SN-lS-79P528 Motor (Motor)
Flywheel [
- 22B RCP Westinghouse SN-3S-79P528 l
Motor (Mcitor) l Flywheel l Safety Bechtel i Inj s:Iction l Piping l Main Steam Bechtel ~ Piping Feedwater Bechtel l Piping Pressurizer Bechtel spray Piping Shutdown Engineers & S-15784B 14135NV 1146 Cooling Fabricators, Heat Inc. Exchanger
- 21 I
[ Containment Bechtel i Spray Piping Shutdown Bechtel Cooling ' Piping Low Pressure Ingersoll-0869-173 l Safety. Rand i Injection Pump #21
l DATE: Sectember 28, 1987 NIS
- PAGE 3
of 6 1 NIS-1 f 8. Examination Dates: ' December 8, 1985 to July 3, 1987 9. ' Inspection Interval: Anril 1, 1977 to ADril 1, 1987 1 f
- 10. Abstract of Examinations:
(Include list of exams and statements concerning status of. work required for current j interval). ] (See Enclosures 2 and 3). The examinations' reported herein constitute the seventh such report of Inservice examination performed at Calvert Cliffs i Unit 2, and ~ the third and final report within the third 40-month period of commercial operation. The examinations { for the'first interval as required by the Long-Term Examina-J tion Plan for Calvert Cliffs. Unit. 2, were performed in q accordance with the 1974 Edition of ASME Code Section XI with 1 Addenda through Summer 1975. Hydrostatic and System Pressure Testing Procedures are available at the plant site for l review. -{ l -l l 1 1 f l l
i DATE: September 28, 1987 NIS-1 PAGE 4 of 6 NIS-1 11. Abstract of Conditions Noted: (See Enclosures 2 & 3) j a. Eddy current examinations of #21 and #22 Steam Generators revealed signs of steam generator tube degradation. Results of #21 Steam Generator examinations showed that of the 8,497 tubes examined, 29 were defective (imperfec-tions 2 40% wall loss), 78 were degraded J> 20 % wall loss, but < 40%), 84 had imperfections (< 20% wall loss), ) and 191' tubes contained service induced denting in the ( ninth support plate on the hot leg side. Inspection of i
- 22 Steam Generator revealed that of the 8,511 tubes
- examined, 14 were defective, 55 were degraded, 62 had imperfections, and 514 tubes contained service induced denting in the ninth support plate on the hot leg side.
l b. The remate visual examination of the Reactor Pressure Vessel (RPV) interior surfaces revealed a misaligned Core Stabil!.zer Snubber Shim Bolt Pin. c. Ultrasonic examinations recorded indications in welds 30-RC-21A-1 and 30-RC-21B-2. Mechanized ultrasonic examinations revealed indications in RPV weld Nos. 2-203A, 2-203B, 2-203C, 9-203, 1-203A, 1-203C, 10-205A, i 4-205A, 4-205B, 4-205C, and 4-205D. I 12. Abstract of Corrective Measures Recommended and Taken: (See Enclosures 2 & 3) a. Those tubes found to contain imperfections greater than j 40% wall loss were removed from service by plugging each end with a mechanical tube plug. Additionally, 18 tubes which showed eddy current indications of less than 40% nominal wall loss were
- plugged, for precautionary reasons.
Five of the 18 tubes were plugged due to degradation at the upper supports, which are suspected to 3 be wear. Twelve tubes were plugged due to degradation above the tube sheet, and one was plugged due to degrada-tion at the first support. Metallurgical examination of U-1 tubing has shown that the degradation above the tube sheet is caused by Intergranular Attack (IGA). The indication at the first support is suspected to be IGA, also. i i a
DATE:. Sectember 28, 1987 NIS i PAGE 5' of 6 1 NIS-1 i l J b. The' misaligned pin was. accepted as is after evaluation. ) c. The indications in 30-RC-21A-1-and 30-RC-21B-2 were. J resolved as code allowable slag inclusions.' The indications in the.RPV. welds were resolved as code q allowable laminar indications-or code allowable j r subsurface' indications. H i l
- 13. NAMES OF INSPECTORS:
R. W. Lawrence, N. S. Hewitt { L i EMPLOYER OF INSPECTORS: Factory Mutual Encineerina l One Bala Plaza Suite 200 Bala Cynwvd,-PA 19004 1 1 l I 'l i l We certify that the Statements made in this report are correct 1 l and the examinations and corrective measures taken conform to'the l rules of the ASME' Code, Section XI. 0 19 07 ~ ~ DATE: l .e SIGNED: [/ Baltimore Gas & Electric. Company. A. R. Thornton General Supervisor.- Plant & Project Engineering. l Cer-ificate of Authorization No..HA Expiration Date UA
l DATE: September 28, 1987 NIS-1 PAGE 6 of 6 NIS-1 l CERTIFICATE OF INSERVICE INSPECTION 6 i I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or l the State or Province of Maryland and employed by Arkwricht-1 Mutual Insurance Company have inspected the components described I in this Owner's Data Report during the period December 8, 1985 to July 3, 1987, 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 Data Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his l employer makes any warranty, expressed or implied, concerning the I examinations and corrective measures described in this Owner's 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 1 inspection. l I DATE: a d Me1-7 19# 7. c'b:kf^/ Ndow w INSPECTOR SIGNATURE / FACTORY MUTUAL SYSTEM COMMISSION: NB 622e , MD 497 National Board State Province and No. l l l i 1}}