ML19310A932
| ML19310A932 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/09/1980 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| IEB-79-14, NUDOCS 8007010043 | |
| Download: ML19310A932 (5) | |
Text
j"dD IMSCORSin Electnc ma comr 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 June 9,1980 t
Mr. J. G. Keppler, Regional Director Office of Inspection and Enforcement, Region III U. S. NUCLEAR REGULATORY COMMISSION 799 f<oosevelt Road Glen Ellyn, Illinois 60137
Dear Mr. Keppler:
DOCKET NOS. 50-266 AND 50-301 FURTHER RESPONSE TO IE BULLETIN 79-14 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 IE Bulletin 79-14 requires licensees to verify that the as-built safety-related piping systems conform to the as-designed seismic analysis and acceptance criteria.
This letter provides a progress report on our Balletin compliance program.
This report is our sixth submittal and supplements our previous responses.
Our March 7,1980 submittal provided a four page table showing the status of the piping stress analysis and pipe support analysis that was in progress at that time.
Since that submittal, the following significant portions of our program have been completed:
a.
As of May 23, 1980, the piping analysis has been completed for 84 of the 85 previously tabulated drawings. The evaluation of the pipe supports has also been completed for these 84 drawings.
b.
Inspections of the piping systems inside the Unit 2 containment structure were completed during the recent April 1980 refueling outage. The inspections started on April 14 and were essentially complete by April 25, 1980. The inspections required about 1700 manhours and included about 7100 feet of pipe and about 700 pipe hangers and supports. While variations from the design drawings were noted during these inspections, all engineering evaluations were completed by April 26 and all systems were judged to be capable of perfonning their function in the event of a seismic occurrence.
c.
Licensee Event Report Numbers80-006 for Unit 1 and 80-004 for Unit 2 were issued on May 5,1980. These reports describe an unacceptable piping connection on the component cooling water jus 13 I 8007010 gg
Mr. J. G. Keppler June 9,1980 piping for both units.
Pipe supports have been installed to assure that this piping meets the acceptance criteria.
The original Point Beach Nuclear Plant acceptance criteria for the seismic stress analysis of pressure piping systems are specified in the PBNP FFDSAR, Appendix A, Table A.3-1, page 3.
The stress limits are clear except for the faulted condition where Table A.3-1 references the design limit curves of WCAP-5890, Revision 1.
These limit curves are shown in Figures 10 through 25 of WCAP-5890 and show various degrees of conservatism depending upon the conditions evaluated. Page seventeen of the WCAP, which is not referenced in the FFDSAR, identifies the piping faulted condition design stress limit as 1.8S.
For our analysis program we have normally met the 1.8S faulted con-dition acceptance criteria.
However there have been five instances where the stress acceptance criterion has been increased to 2.4S. We consider that the higher faulted condition acceptance criterion is justified, on a case-by-case basis, for the following reasons:
Use of the original PBNP seismic response spectra utilized only a.
0.5% damping which is conservative.
Current NRC regulatory guides allow higher damping factors.
b.
The current corresponding ASME Code stress acceptance criterion is 2.4S.
The completion of the piping inspections in the Unit 2 containment has added about 33 piping isometric drawings to our analytical program; thus, the total number of isometric drawings in the PBNP IE Bulletin 79-14 program is presently 118. In total, these drawings describe over 33,000 feet of pipe and more than 3000 pipe supports.
Attached hereto is an updated analytical schedule for the remaining portion of our program. This attachment supplements that contained in our March submittal and identifies only those drawings which were not fully com-pleted as of May 23, 1980. The attached schedule indicates that all remain-ing piping stress and pipe support analyses will be completed by about September 30, 1980. Accordingly, we anticipate that our next report will be submitted in October 1980.
If you require any additional information at this time, please contact us.
Very truly your.s, f'
C. W. Fay, Director Nuclear Power Department Attachment Copies to: Office of Inspection and Enforcement Division of Reactor Operations Inspection Mr. A. Schwencer, Chief Operating Reactors Branch 1 NRC Resident Inspector Point Beach Nuclear Plant
POINT BEACH NUCLEAR PLANT STATUS OF STRESS ANALYSIS & PIPE SUPPORT REVIEW FOR NRC IE BULLETIN 79=14 (5/23/80 ISSUE)
STATUS OF PIPE SUPPORT STRESS PIPING LOCATION STATUS OF REVIEW OR
' APPROXIMATE 150. DWG.
INSP.
SYSTEM UNIT UNIT STRESS ANALYSIS DATEl ANALYSIS MODIFICATIONS' NO.
PKG. NO.
LINE NO.
1 2
OR DATE (Ali. BEC)
BY REQUIRED A.
Drawings Also Tabulated in 3/7/80 Submittal P-105 7-2 WD-151R-8 0
Done Done W/BEC 10 0
7A WD-151R-8 I
I EMBEDED 105 WD-151R-8 0
6/13/80 6/27/80 BEC P-113 1-2 HB-19 0
6/3/80 6/6/80 BEC-JB P-215 1-5 HB-19 0
Done Done BEC-JB 3
215 HB-19 I
6/20/80 7/11/80 BEC P-216 1-5 HB-19 0
Done Done BEC-JB 1
216 HB-19 I
6/20/80 7/11/80 BEC P-219 25 SI-1501R-1 0
Done Done W
4
& -3 219 (Same)
I 7/18/80 8/8/80 BEC P-220 25 SI-1501R-1 0
Done Done W
(See P-219) 220 (Same)
I 7/18/80 3/8/80 BEC P-232 30 AC-60lR-1, 0
Done Done W
6
-2, -3 232 SI-151R-X I
7/7/80 8/l/80 BEC B.
New Listings 0
To Be Assigned 38 CH-60lR 0
Not required; O variations i
P-159 4
JG-4 Common Done Done BEC-JB 5'
(non-seismic)
P-163 163 HB-19 in Common 7/18/80 8/8/80 BEC Pumphouse P-165 165 SFC,4,
-5, Common 8/22/80 9/19/80 BEC
.-6,
-7, & 11 (Pumps to Pool)
Page 1 of 3
POINT BEACH NUCLEAR PLANT STATUS OF STRESS ANALYSIS & PIPE SUPPORT REVIEW FOR NRC IE BULLETIN 79-14 (5/23/80 ISSUE)
STATUS OF PIPE SUPPORT STRESS PIPING LOCATION STATUS 0F REVIEW OR APPROXIMATE ISO. DWG.
INSP.
SYSTEM UNIT UNIT STRESS ANALYSIS DATEl ANALYSIS MODIFICATIONS NO.
PKG. NO.
LINE NO.
1 2
OR DATE (ALL BEC)
BY REQUIRED P-166 166 SFC-1,
-2, Comon 8/22/80 9/19/80 BEC
& -3 P-167 167 Steam to Evap. Comon 8/22/80 9/19/80 BEC (SA-601)
P-168 168 SWP-4,
-5,
-6, Common 8/22/80 9/19/80 BEC
& -7 (From HXs to JB-2)
P-169 169 SWP-1,
-2, Common 8/29/80 9/26/80 BEC
& -3, (From HB-19 to HXs)
P-170 170 Gas Stripper Common 8/29/80 9/26/80 BEC CH-19-152Q P-171 171 Gas Stripper Common 8/29/80 9/26/80 BEC CH-18-152Q P-208 208 EB-1 I
7/18/80 8/18/80 BEC P-212 212 EB-9 I
6/27/80 7/18/80 BEC P-218 218 SI-2501R-4 I
6/20/80 7/11/80 BEC RC-250lR-5 P-226 226 SI-301R-1 I
7/25/80 8/15/80 BEC P-229 229 SI-301R-1 I
8/8/80 8/29/80 BEC P-230 230 AC-152N-4 I
6/27/80 7/18/80 BEC P-236 236 SI-60lR-2 I
7/25/80 8/15/80 BEC-SI-250lR-5 RC-250lR-5 P-237 237 SI-902R-1 I
7/25/80 8/29/80 BEC SI-250lR-1 SI-250lR-2 RC-250lR-7 P-238 238 HB-19 I
7/7/80 8/1/80 BEC P-?39 239 EB-10 I
6/20/80 7/18/80 BEC Page 2 of 3
POINT BEACH NUCLEAR PLANT STATUS OF STRESS ANALYSIS & PIPE SUPPORT REVIEW FOR NRC IE BULLETIN 79-14 (5/23/80 ISSUE)
STATUS OF PIPE SUPPORT STRESS PIPING LOCATION STATUS OF REVIEW OR APPROXIMATE ISO. DWG.
INSP.
SYSTEM UNIT UNIT STRESS ANALYSIS DATEl ANALYSIS MODIFICATIONS NO.
PKG. NO.
LINE NO.
I 2
OR DATE (ALL BEC)
BY REQUIRED P-242 242 EB-10 I
6/20/80 7/18/80 BEC P-243 423 RC-2501R-1 I
7/7/80 8/8/80 BEC P-244 244 RC-250lR-2 I
7/7/80 8/8/80 BEC P-245 245 RC-250l R-Z I
7/7/80 8/8/80 BEC P-246 246 RC-2501R I
8/8/80 8/29/80 BEC Connections P-247 247 CH-60lR-1 I
6/20/80 7/11/80 BEC P-248 248 AC-60lR-2 I
6/20/80 8/29/80 BEC AC-60lR-6 AC-2501R-1 P-250 250 AC-152N-4 I
6/20/80 7/18/80 BEC P-251 251 AC-152N-4 I
8/18/80 9/2/80 BEC P-254 254 CH-250lR-4 I
8/8/80 9/2/80 BEC P-257 257 PA-151 R-1 I
8/8/80 9/2/80 BEC P-258 258 Main Coolant I
Not required; O variations 0
P-262 262 RC-60lR-2 I
7/15/80 8/8/80 BEC (non-seismic)
DEFINITIONS:
I
- Inside Containment W
- Westinghouse Electric Corporation 0
- Outside Containment JB - Subcontractor to Bechtel BEC - Bechtel Power Corporation 1.
The completion of the pipe support review means that the number and type of modifications, if required, are known but drawings for construction are not yet available.
Page 3 of 3
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