ML19274F848
| ML19274F848 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 08/01/1979 |
| From: | Bixel D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| IEB-79-14, NUDOCS 7908160359 | |
| Download: ML19274F848 (5) | |
Text
.A s,/ ' v h T
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power Company cener.: omces: 2,2 w..
uicn, gen Avenue. Jachtmon Michigen 49201 e Area Code 517788 0550 August 1, 1979 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-155 - LICEIiSE DPR BIG ROCK POINT PLANT - INSPECTION PLAN IN RESPONSE TO IE BULLETIN 79-14:
SEISMIC ANALYSES FOR AS-BUILT SAFETY-RELATED PIPING NRC letter dated July 2, 1979 transmitted the subject Bulletin; Revision 1 was subsequently provided by NRC letter dated July 20, 1979 The subject Bulletin requested that safety-related piping be inspected to verify that the as-built condition conforms to design requirements. An inspection plan was requested within 30 days of the date of the original Bulletin.
The inspection plan to be utilized at Big Rock Point to address the concerns raised by the subject Bulletin is forwarded as an attachment to this letter.
/
David A Bixel Nuclear Licensing Administrator CC Director, Office of Nuclear Reacter Regulation Director, Office of Inspection and Enforcement
/Itp q 9 0818 "
SEISMIC ANALYSIS FOR AS-BUILT SAFETY-RELATED PIPING SYSTEMS FOR BIG ROCK POINT NUCLEAR PLANT CONSUMERS POWER COMPANY 1.
INTRODUCTION USNRC IE Bulletin 79-14 dated July 2, 1979, including revision 1 dated July 18, 1979, requested that certain information be provided within 30 days of July 2, 1979.
The Consumers Power Company (CPCo) response regarding the Big Rock Point Nuclear Plant (BRP) is contained in the following sections.
Present planning is to define the safety related piping to be evaluated on drawings similar to the P &
ID's listed in Attachment A.
That piping which is designated will be evaluated to a confidence level (at least 50%), and if no significant deviations are found, the evaluation may be terminated.
The drawings designating the piping considered for evaluation will be provided to the NRC to facilitate review on or about August 15, 1979.
2.
BRP SEISMIC DESIGN The Final Hazards Summary Report (FHSR) for BRP discusses Seismology (see Section 2.6).
While seismic design factors were utilized in the design of certain BRP structures, design of all piping systems except the Reactor Depressurization System (RDS) did not reflect seismic factors because the BRP site is located in an area of low earthquake intensity (Ref. Section 12.10.3 of the BRP FHSR).
Thus, verification that seismic analysis input information conforms to the actual configuration of safety related systems is not appropriate for BRP except for the RDS System.
The RDS System piping was installed after initial plant operation and a seismic analysis was performed on that system.
The following input documents were used:
A.
Piping Geometry - CPCo Drawing 0740G41004, Rev E (9-28-77) and drawings referenced thereon.
Page 1 of 3
B.
Pressure and Temperature - Suntac Specification 3490-1300-501, Rev 2, dated 7-1-77.
C.
Components - Various owner and vendor drawings for valves, supports, etc.
These are on file.
D.
Seismic Response Spectra - Suntac Specification 34490-1300-501, Rev 2, dated 7-1-77.
E.
Pipe and Fitting Schedule - Suntac Specification 34490-1300-503, Rev 2, dated 2-7-75.
3.
BRP PIPING SYSTEM DESIGN REQUIREMENTS Indications are that the BRP piping design included deadweight and flexibility considerations.
A requirement for the primary coolant piping is presented in Amendment 8 to the BRP FHSR.
4.
SYSTEM IDENTIFICATION The current BRP piping systems were reviewed and those having safety related piping are listed in Attachment A.
Attachment A also lists the P & ID number.
5.
PRIMARY COOLANT SYSTEM A primary coolant system flexibility analysis is presented in Amendment 8 of the FHSR.
The analytical results show that the stresses do not exceed allowable stresses.
The primary coolant system piping is suspended in a manner such that the pipe stress is relatively insensitive to the exact location of hangers and exact piping dimensions.
In addition, this system has undergone many cycles of heatup and cooldown over a period of 17 years without apparent adverse effects.
Therefore, due to the above and due to ALARA considerations, the primary coolant piping will not be inspected.
- However, the number, type and general location of hangers will be reviewed against drawing requirements and spring hanger loads will be verified to be within the range of requirements as specified on the design drawings.
6.
INSPECTION ITEMS The selected safety related portions of piping systems will be inspected against isometrics used in the flexibility calculations and existing piping drawings to verify agreement between the installed systems and configurations used in analysis.
Page 2 of 3
Those portions of safety related systems for which no flexibility calculations can be found will be inspected
'l to verify agreement between installed systems and existing drawings.
Consumers Power Company believes all safety related piping was analyzed and supported to assure adequate flexibility.
Those portions of the safety related systems
',r which no flexibility calculations can be found will be ide tified and the implications.
resolved.
The following items will be verified:
A.
Pipe run geometry B.
Support and restraint design, location, functions and clearance C.
Embedments D.
Pipe attachments E.
Valve and 'alve operator location and orientation A variety of inspection methods will be used such as measuring tape (or similar measuring equipment) for piping geometry, visual comparison of piping supports with the support drawings, etc.
Insulation will not be removed to facilitate inspection.
7.
SCHEDULE FOR INSPECTION OF SYSTEMS BRP is presently not in service and is expected to return to operation in September 1979.
Because of ALARA considerations, priority will be given initially to those areas of inspection which would have higher radiation levels if inspected during operation.
- Also, the time span between receipt of IE Bulletin 79-14 and August 15, 1979, is needed to gather drawings and data, develop procedures, and mobilize personnel at the site in preparation for inspection.
Present scheduling is for the inspection to begin on or about August 15, 1979, and to be completed by October 31, 1979.
Thus, the guidelines of NRC IE Bulletin 79-14 relating to schedule, redundant and non-redundant systems may not be adhered to.
Page 3 of 3
I ATTACHMENT A IDENTIFICATION OF SYSTEMS WITH SAFETY PIPING 0740G40106 Steam & Condensate System 0740G40107 Reactor Cleanup, Shutdown & Poison System 0740G40108 Radwaste System 0740G40lll Circulating, Cooling & Services Water Systems 0740G40121 Nuclear Steam Supply System 0740G40122 Control Rod Drive System 0740G40123 Fire and Post incident Cooling System 0740G40125 Ventilating, Heating & Cooling System 0740G41003 Reactor Depressurazation System