ML19323C466
| ML19323C466 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 04/17/1980 |
| From: | Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| IEB-79-14, NUDOCS 8005150568 | |
| Download: ML19323C466 (8) | |
Text
8 005150 TN 77c
.M CORSumBIS POVict company General Off ces: 212 West Michigan Aver ve, Jackson, Michigan 49201
- Area Code S17 788-0550 April 17, 1980 Mr James G Keppler Office of Inspection and Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DCCKET 30-155 - LICENSE DPR BIG ROCK POINT PLANT - REVISION TO CONSU11ERS POWER COMPANY SUBMI' ITAL DATED OCTOBER 31, 1979 -
RESPONSE TO IE BULLETIN 79-14:
7.ISMIC ANALYSIS FOR AS-BUILT SAFETY-RELATED PIPING Attached please find Revision 1 (dated April 2, 1980) to Consumers Power Company's October 31, 1979 120-day response to IE Bulletin 79-14.
Revised portions of the text are indicated by a vertical line in the right margin.
Please remove the affected pages and insert the updated pages provided.
This revision was necessitated as a result of concern raised by an NRC I&E inspector's visit shortly after work relating to tae reference bulletin was completed by Consuears Power Company.
The NRC I&E inspector's concern centered around that portion of the Reactor Depressurization System (RDS) piping from the safety relief valves to the steam drum enclosure wall which was not included in our safety analysis.
However, the inspector insisted that this portion of piping was a continuation of the RDS piping which is safety-related and indicated we should inspect same. The inspection was done with the results shown in the ee.tachment.
y David P Hoffman Nuclear Licensing Administrator CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement Attachment Final Response to IE Bulletin 79-14 APR 2 41988
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CRP/79-14 R;vicion 1 April 2,1980 Table of Contents Page 1.
INTRODUCTION 1
2.
ORGANIZATION 1
3.
SYSTEM IDENTIFICATION 2
4.
INSPECTION 2
A.
Period of Inspection 2
B.
Elements of Inspection 2
C.
Results of Inspection 3
D.
Insulation Removal 3
E.
Primary Coolant System 4
F.
Accessibility 4
G.
Verificatien of Pipe Wall Thickness and Pipe Welds 5
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H.
ADDITIONAL INSPECTION Sa 1
5.
ANALYSIS 6
A.
Flexibility Analysis 6
B.
Seismic Analysis 6
6.
NONCONFORMANCES 7
7.
RESOLUTION OF INSPECTION ITEMS 7
8.
CONCLUSIONS 7
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BRP/79-14 Revicicn 1 April 2,1980 3.
SYSTEM IDENTIFICATION Current BRP systems were reviewed, and those systems having safety-related piping are listed below, along with the applicable Piping and Ittstrumentation Diagram (P&ID) drawing numbers.
P&ID SYSTEM 0740G40106 Steam and condensate system 0740G40107 Reactor cleanup, shutdown, and poison system 0740G40108 Radwaste system 0740G40lli Circulating, cooling, and service water systems 0740G40121 Nuclear steam supply system 0740G40122 Control rod drive system 0740G40123 Fire and post-incident cooling system 0740G40125 Ventilating, heating, and cooling system 0740G41003 Reactor depressurization system Appendix D of this report provides reduced copies of the record drawings which delineate the boundaries of safety-related piping in the various systems.
4.
INSPECTION A.
PERIOD OF INSPECTION Inspection was performed at BRP during the period from August 15, 1979, to November 10,1979.
Approxi-1 mately 6,000 feet of pipe and 420 supports were inspected as well as the associated in-line components (valving, etc).
B.
ELEMENTS OF INSPECTION i
1)
The inspection was performed according to Field Procedure 1 which is included as Appendix E of this report.
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2)
The essential items verified by the inspection are as follows:
1 a)
Pipe geometry 1
b)
Support design, location, function, and clearance c)
Embedments d)
Pipe attachments 2
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R3vicion 1 April 2, 1980 H.
ADDITIONAL INSPECTION In addition to the piping designated in Drawing 0740G41003 (see Appendix D), piping from the safety relief valves.
j (SV-4984, -4985, -4986, and -4987) to the steam drum en-closure wall was inspected.
This additional ' inspection was suggested by the Region III inspector in an inspec-tion meeting on November 7,1979, at BRP.
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APPENDIX P EVALUATIONS OF ITEMS NOTED DURING INSPECTION (continued)
Daily CPCo Discrepancy P&ID Drawing Item Noted Item Report System for System During Inspection Resolution 141 27 Reactor 0740G41003 The design drawing is unclear.
The existing piping configuration has depres-It appears to show that support been compared to the configuration surization PS-109 is attached to line 103D used in the piping analysis, and the at the platform. Support PS-109 difference is acceptable.
is actually located above the platform.
142 27 Reactor 0740G41003 Details in Drawing 0740G11003 for The difference in clearance is not depres-PS-110 supports call for a significant and is acceptable, surization 1/16-inch clearance between the Additionally, the clearance will pipe and pipe clamp. Clearances decrease when the system is operating.
in all cases are greater, averag-ing 1/4-inch (pipe was cold when measured).
143 27 Reactor 0740G41003 Lock nuts on the two 1-1/2-inch These nuts have been tightened.
depres-through bolts on support PS-113 surization are loose.
1 144 27 Reactor 0740G41003 The restraint detail in Draw-The additional length and nuts do not
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depres-ing 0740G11003 calls for pipe affect the function of the restraint surization clamp bolts to be single nutted, and are acceptable.
2-1/2 inches in diameter, and 10-1/2 inches long on all eight PS-110 supports. All are actually double nutted, with a 2-1/2-inch diameter and 17-inch length.
.s s-145 27 Reactor 0740G41003 The design drawing indicates These differences do not affect the depres-that base plates for PS-110 support function and are acceptable.
surization supports are typical (35 inches long from end to end and j
5 inches from the end to the centerline of the bolt hole).
The four restraints on the C and D lines do not conform I
(31 inches long from end to end, sun
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APPENDIX F EVALUATIONS OF ITEMS NO' ED DURING INSPECTION (continued)
T Daily CPCo Discrepancy PEID Drawing Item Noted Item Report System tor System During Inspection Resolution 2-1/2 inches from one end to the bolt centerline, and 5 inches from the opposite end to the bolt centerline).
146 27 Reactor 0740G41003 The design drawing shows a Because of the relatively close depres-distance of l'-9" from the pipe spacing of supports on these lines, surization centerline to the top of the the dimensional change has an insig-grout under the base plate for nificant effect and is acceptable.
PS-110 supports. Measured dis-Grouting is as specified on the tance from the pipe centerline drawing.
to the wall was 25 inches for the four PS-110 supports on lines A and B, and 23 inches for the upper PS-110 support on line C.
Grout thicknesses ranged from 3/4 inch to 1-1/2 inches.
147 27 Reactor 0740G41003 The lower PS-110 support on line A Anchor bolt evaluation was performed i
depres-had no washers under the nuts on in accordance with U.S. NRC IE surization two anchor bolts. The bottom two Bulletin 79-02.
holes in the base plate appear to have been enlarged with a cutting torch and are partially visible around the nuts.
'148 27 Reactor 074DG41003 The design drawing for PS-112 Anchor bolt evaluation was performed depres-supports indicate that the in accordance with U.S. NRC IE surization anchor bolts on the base platesBulletin 79-02.
have single nuts with washers.
PS-ll2 supports on lines B, C, and D have double nuts with no washers. The PS-112 support on line A has three bolts with j
double nuts and no washers, and one bolt with a single nut and no washer.
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APPENDIX F EVALUATIONS OP ITEMS NOTED DURING IHSPECTION (continued)
CPCo Daily Discrepancy PEID Drawing Item Noted item Report System for System During Inspection Resolution 149 27 Reactor 0740G41003 The east corner of the lower base Anchor. bolt evaluation was performed I
depres-plate on support PS-113 was cut in accordance with U.S. NRC IE surization off so that it would fit beside Bulletin 79-02.
another base plate.
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