ML20058D589

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Submits Response to 820312 Request for Addl Info Re Inservice Insp Program
ML20058D589
Person / Time
Site: Calvert Cliffs  
Issue date: 07/22/1982
From: Lundvall A
BALTIMORE GAS & ELECTRIC CO.
To: Clark R
Office of Nuclear Reactor Regulation
References
NUDOCS 8207270224
Download: ML20058D589 (13)
v • d • e


Text

{{#Wiki_filter:. t A BALTIMORE e GAS AND ELECTRIC CHARLES CENTER. P.O. BOX 1475

  • BALTIMORE, MARYLAND 21203 ARTHUR E. LUNDVALL. JR.

ys ggg vice pacs.ocur sumv U.S. Nuclear Regulatory Commission Division of Licensing Washington, DC 20555 ATTENTION: Mr. Robert A. Clark, Chief Operating Reactors Branch #3

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Inservice inspection Program

REFERENCE:

(a) Letter to Mr. A. E. Lundvall, Jr., f rom Mr. R. A. Clark dated March 12,1982 Gentlemen: Reference (a) requested that Baltimore Gas and Electric Company provide additional information concerning the Inservice Inspection Program for Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2. This information is provided below. I. PROGR AM INTERVAL / ADDITIONAL RELIEF REQUESTS BG&E concurs that the first ISI program interval will conclude May 8,1985, for Calvert Cliffs Unit I and April 1,1987, for Calvert Cliffs Unit 2. The intervals may be extended as much as one year to be concurrent with plant outages, as permitted by IWA-2400. Presently 10 CFR 50.55a will require us to update to the year and addenda of the Code incorporated no longer than twelve (12) months prior to the beginning of the l next interval. This means that each unit could be required to update to different year and addenda of ASME Code Section XI. In an affort to reduce procedure duplication and confusion of Code requirements between Calvert Cliffs Units 1 and 2 it is preferred that we update both units to the same year and addenda of ASME Code Section XI. In order to insure updating of both plants' ISI programs to the same year and addenda for the remaining service lifetime, it is proposed to extend the Unit I first interval to April 1,1987. This will extend the first interval by one refueling outage l as shown below. OYA l I l l t 8207270224 820722 l PDR ADOCK 05000317 l G PDR

F 1 Mr. Robert A. Clark July 22,1982 Page 2 PREDICTED REFUELING OUTAGES UNIT 1 UNIT 2 Spring 1982 Fall 1982 Fall 1983 Spring 1984 Spring 1985 Fall 1985 0 Fall 1986 Spring 1987 Last outage in inspection interval. O Proposed last outage in inspection interval if Unit I updates April 1,1987. As stated above, the Code presently allows a shift of the interval by twelve (12) months. By approving the April 1,1987, date for both units the interval for Unit I will be extended approximately eighteen (18) months. Accordingly, both units will be allowed to update to the same year and Addenda of the Code for the remaining operating service. Should such a change in interval completion dates meet with your approval, please inform us such that we may submit an additional exemption request. II. REACTOR PRESSURE VESSEL CLOSURE HEAD DOLLAR PLATE WELD NO. 6-209B Due to Control Rod Drive Mechanism penetrations and assemblies, this weld is inaccessible for inspection. The relief requested for deleting this weld examination may be further emphasized by the enclosed Combustion Engineering drawings 233-415 and 233-427 and Transco drawing DR3854-71. Attempts have been made in past inspection outages to access this weld for examination but unsuccessfully. Later editions of ASME Code Section XI permit deletion of inaccessible reactor vessel head welds. III. ENCAPSULATED MAIN STEAM AND FEEDWATER LINES This exemption request addressed welds on Main Steam and Feedwater lines that are encapsulated and, therefore, inaccessible for inspection. The exemption was submitted to clarify a conflict in inspection requirements for the Class 2 portions of these lines that extend from the Containment Building to the first valve that is closed or capable of automatic closure. ASME Code Section XI inspection requirements differ from an augmented inservice inspection program incorporated in Calvert Cliffs Technical Specifications. For Class 2 portions, ASME Code Section XI requires that an equivalent of 100% of the welds in one of the multiple streams of these systems be examined over the course of 40 years distributed between both of the multiple streams. Calvert Cliffs Technical Specification 4.4.10.1.2, Unit I and 2, prescribes an Augmented Inservice Inspection Program which requires the unencapsulated welds greater than four (4) inches in nominal diameter in the main steam and main feedwater piping runs located outside the containment and traversing safety related areas or located in compartments adjoing safety related areas be inspected 100% every 10-year inspection interval.

Mr. Robert A. Clark July 22,1982 Page 3 All Class 2 portions of Main Steam and Feedwater piping that are located outside of the containment fall under the augmented inspection requirements in Calvert Cliffs Technical Specifications. Since Technical Specifications supersede ASME Code Section XI requirements, only the augmented program applies to these portions of Class 2 Main Steam and Feedwater piping. Therefore, this particular exemption request was never required since we are in compliance with the Technical Specifications. Accordingly, we withdraw this particular exemption request. To answer your specific questions concerning the request: (a) (1) Weld 34-MS-1201-5 was a typographical omission and should have appeared between 34-MS-1201-5LU-2 and 34-MS-1201-5LD on the inaccessible list. (2) Weld 34-MS-1201-8LD-l&2 should have been listed as inaccessible. (3) Weld 34-MS-1202-12LD should have been listed as inaccessible only. (b) None of these welds should have been listed as requiring examination per ASME Code Section XI because they are located on non-class portions of the line. Weld 34-MS-1201-10LD will be inspected per our augmented inspection program. (c) We do utilize the multiple stream exemptions allowed for these systems in the containment, but follow the augmented inpsection program for these systems extending outside of the containment building. (d) The first listing of 34-MS-1202-15LD was a typographical error and should have been 34-MS-1202-14LD. Below is a corrected listing of Class 2 welds that are encapsulated and additional welds that are examined by the augmented inspection program but are on non-class portions of the piping. INACCESSIBLE CLASS 2 WELDS UNIT 1 MAIN STEAM i l 34-MS-1201-2 34-MS-1202-2 34-M S-1201-3 34-MS-1202-3 34-MS-1201-3LD 34-MS-1202-3LD l 34-MS-1201-4LU 34-MS-1202-4LU i 34-MS-1201-4 34-M S-1202-4 34-MS-1201-4LD-1 34-M S-1202-4LD-1 l 34-MS-1201-4LD-2 34-MS-1202-4LD-2 34-MS-1201-5LU-l 34-MS-1202-5LU-l 34-MS-1201-5LU-2 34-MS-1202-5LU-2 34-MS-1201-5 34-MS-1202-5 l l I

r Mr. Robert A. Clark July 22,1982 Page 4 INACCESSIRLE CLASS 2 WELDS UNIT 1 M AIN STEAM (CONT) 34-MS-1201-5LD 34-MS-1202-5/6-MS-1008 34-MS-1201-6LU 34-MS-1202-5BC-2 34-MS-1201-6L 34-MS-1202-6LU 34-MS-1201-6LD 34-M S-1202-6 34-MS-1201-6/6-MS-1207 34-MS-1202-6LD 34-MS-1201-6-BC-3 34-MS-1202-7LU 34-MS-1201-7LU 34-MS-1202-7 34-MS-1201-7 34-MS-1202-7LD i 34-MS-1201-7LD-1 34-MS-1202-8LU 34-MS-1201-7LD-2 34-MS-1202-8 34-MS-1201-8LU-l 34-MS-1202-8LD-1 34-MS-1201-8LU-1 34-M S-1202-8LD-2 34-MS-1201-8 34-MS-1202-9LU-l 34-MS-1201-8LD-1 34-MS-1202-9LU-2 34-MS-1201-8LD-2 34-MS-1202-9 34-MS-1202-9LD-1 34-MS-1202-9LD-2 INACCESSIBLE CLASS 2 WELDS UNIT 1 FEEDWATER 16-FW-1201-1 16-FW-1202-1 16-FW-1201-2 16-FW-1202-2 16-FW-1201-3 16-FW-1202-3 16-FW-1201-4 16-FW-1202-4 16-FW-1202-5 16-FW-1202-6 16-FW-1202-7 16-FW-1202-8 16-FW-1202-9 16-FW-1202-10 l

F Mr. Robert A. Clark July 22,1982 Page5 INACCESSIBLE CLASS 2 WELDS UNIT 2 MAIN STEAM 34-MS-2001-ILU 34-MS-2002-lLU 34-MS-2001-1 34-MS-2002-1 34-MS-2001-lLD1 34-MS-2202-lLDI 34-MS-2001-lLD2 34-MS-2002-ILD2 34-MS-2001-2LU 1 34-MS-2202-2LU1 34-MS-2001-2LU2 34-MS-2002-2LU2 34-MS-2001-2 34-MS-2002-2 34-MS-2001-2LD 34-MS-2002-2LD 34-MS-2001-2/4-MS-2009 34-MS-2002-2/6-MS-2008 34-MS-2001-2/6-MS-2007 4 34-MS-2002-2/4-MS-2010 34-MS-2001-3LU 34-MS-2002-3LU 34-MS-2001-3 34-MS-2002-3 34-MS-2001-3LD 1 34-MS-2002-3LD 1 34-MS-2001-3LD2 34-MS-2002-3LD2 34-M S-2001-4LU 1 34-MS-2002-4LU 1 34-MS-2001-4LU2 34-MS-2002-4LU2 34-MS-2001-4 34-M S-2002-4 34-MS-2001-4LD 1 34-MS-2002-4LD 1 34-MS-2001-4LD2 34-MS-2002-4LD2 INACCF3SIBLE CLASS 2 WELDS UNIT 2 FEEDWATER 16-FW-2001-1 16-FW-2002-1 16-FW-2001-2 16-FW-2002-2 i 16-FW-2001-3 16-FW-2002-3 i 16-FW-2002-4 16-FW-2002-4 16-FW-2002-5 16-FW-2002-6 16-FW-2002-7 16-FW-2002-8 16-FW-2002-9 l I i

Mr. Robert A. Clark July 22,1982 Page 6 ADDITIONAL WELDS TO BE EXAMINED PER TECH SPEC. 4.4.10.1.2 UNIT 1 MAIN STEAM 34-MS-1201-10LD 34-MS-1202-13LU 34-MS-1201-1ILU 34-MS-1202-13 34-MS-1201-l l 34-MS-1202-13LD 34-MS-1201-11LD 34-MS-1202-14LU 34-MS-1201-12LU 34-MS-1202-14 34-MS-1201-12 34-MS-1202-14LD 34-MS-1201-12LD 34-MS-1202-15LU 34-MS-1201-13LU 34-MS-1202-15 34-MS-1201-13 34-MS-1202-15LD 34-MS-1201-13LD-1 34-MS-1202-16LU 34-MS-1201-13LD-2 34-M S-1202-16 34-MS-1201-14LU-1 34-MS-1202-16LD 34-MS-1201-14LU-2 34-MS-1202-16BC 34-MS-1202-17LU 34-M S-1202-17 34-MS-1202-17LD-1 34-MS-1202-17LD-2 34-MS-1202-18LU-1 34-MS-1202-18LU-2 UNIT 2 MAIN STEAM 34-MS-2001-6 34-MS-2002-6 34-MS-2001-7LD 34-MS-2002-8LD 34-MS-2001-8 34-MS-2002-9 l 34-MS-2001-8LD 34-MS-2002-9LD 34-MS-2001-8BC 34-M S-2002-9BC 34-MS-2001-9 34-M S-2002-10 34-MS-2001-9LD-1 34-M S-2002-10LD-1 34-MS-2001-9LD-2 34-MS-2002-10LD-2 34-MS-2001-10 34-M S-2002-I l 34-MS-2001-10LD-1 34-M S-2002-11 LD-1 34-MS-2001-10LD-2 34-MS-2002-I ILD-2 TOTAL CLASS 2 WELDS NUMBER ENCAPSULATED % ENCAPSULATED U-l Main Steam 113 52 46 U-l Feedwater 50 14 28 U-2 Main Steam 103 40 39 U-2 Feedwater 44 12 27

r Mr. Robert A. Clark July 22,1982 Page 7 IV. HYDROSTATIC TESTING OF NON-NUCLEAR SYSTEMS When this exemption request was submitted it was incorrectly assumed that any containment penetration piping was at least considered Class 3. It has since been learned that a Non-Class system penetrating the containment remains non-class, although it is subject to special testing as required by 10 CFR 50 Appendix 3. Later construction codes have special requirements for containment penetration piping. At the time Calvert Cliffs was constructed, penetration piping for the most part was upgraded to meet the requirements of B 31.7 Class 2, although the remaining system may have been non-class B 31.1. Proper reclassification is being accomplished and the need for this exemption no longer exists. V. HYDROSTATIC TESTING OF HYDR AULIC ACTUATOR LINE FOR MAIN STEAM ISOLATION VALVES Hydrostatic testing of this system is not required by the Code and, therefore, the exemption request is no longer required. Regulatory Guide 1.26 applies to components containing radicactive material, water or steam. It adds that systems not covered by the Regulatory Guide should be fabricated, erected, and tested to quality standards commensurate with the safety function to be performed. The main steam isolation valves are tested in accordance with ASME Code Section XI Subsection IWV and Calvert Cliffs Technical Specifications. These testing requirements provide assurance of the integrity and functional operability of the hydraulic actuator system. Should you have any further questions concerning Calvert Cliffs Inservice Inspection Program, please do not hesitate to contact us. Very truly yours, / /Q:',), JwL Vice President - Supply AEL/BCR/gla Enclosures cc:

3. A. Biddison, Esquire G. F. Trowbridge, Esquire D. H. Jaffe, NRC R. E. Architzel, NRC l

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