ML20003H527
| ML20003H527 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/07/1981 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-79-14, TAC-42636, NUDOCS 8105060275 | |
| Download: ML20003H527 (6) | |
Text
,
~j f
'Af ein 4ss eooo
=x m,.
April 7, 1981
- MyUD United States Nuclear Regulatory Consnission 8
,\\
bp pf ',J l j,,,) g j,. h ' O Office of Inspection and Enforcement
[
g Attn:
Boyce H. Grier, Regional Director p
sa Region I 2 WtY 0 4198:
~
631 Park Avenue
- " Wf** [
King of Prussia, Pennsylvania 19406 E
Reference:
Beaver Valley Power Station, Unit No. 1 Th Docket No. 50-334, License No. DPR-66 p
IE Bulletin.79-14 Gentlemen:
In accordance with our letter dated October 20, 1980, we are submitting a report concerning our activities associated with IE Bulletin 79-14.
This is not a final report since the equipment nozzle information is incomplete due to the need for vendor responses which are outstanding.. (See Attachment B.)
Duquesne Light Company has undertaken the appropriate actions to provide assurance that the seismic stress analysis of the safety related piping systems 2-1/2" and larger reflect the as-built conditions of the plant and demonstrate acceptability.of the subject piping.
Five engineering firms were employed to provide sufficient turn-around of this effort. Duquesne Light provided coordination of the total effort and direct supervision of the field inspection and record search personnel.
The tasks entailed the review or analysis of 234 isometric drawings and 2,599
~
suppdrt designs associated with 251 computer pipe stress analyses. All vendors used approved versions of Nuclear Services Corporation's Nupipe Pipe Stress computer program. There were 211 pipe and support stress analysis packages issued for this effort.
l The data base for this effort consisted of marked up Isometric and support drawings developed by field inspection of as-built conditions plus as-built material packages.
A list of the isometric drawings defining the scope of the effort was previously sent to you. The as-built material packages were issued on an isometric basis and are a compilation of the results of researching the QC records.
810506027 5
Beavar Vall1;y Powar Station, Unit No.1 D6cket No. 50-334, Lic:nss No. DPR-66 IE Bulletin 79-14 Page 2 The information transmitted to the analysts is categorized into two types that involve actual physical measurement and the remaining involving searching Quality' Control and Engineering records. The following is the categorization of the major elements of the as-built information:
Obtained by Physical Measurement
- 1) All piping and support geometry (except pipe wall thickness and drilled in anchor base plates, see IEB 79-02 report) 2)
All pipe to support clearances
- 3) All insulated hangers (all insulated hangers were exposed)
Obtained by Searching Quality Control and Engineering Records
- 1) Valve and equipment parameters
- 2) Materials of construction The as-built material packages delineated infomation obtained from searching the microfilmed documents from the shop's or field fabricator's purchasing records, welding records and field change records. In some instances, the various data sources conflicted. When this occurred, the most conservative parameter was assumed applicable to the loading type in question.
There were a few areas where physical measurements or adequate records could not be obtained. Some areas had high radiation levels or were difficult to get to physically. Where possible, visual inspection data was used.
Attachment A delineates the percentages of the total effort for which the geometric as-huilt information was not complete.
It was determined that the documentation associated with pipe support I
materials indicated that it was supplied per Manufacturer's Standards Society l
Specification MSS-SP-58 and 69.
Certificates of Compliance (C0C) or Certified l
Mill Test Reports (CMTR) for the pipe support material could not be found.
The original specification used to purchase the support material did not require these documents to Be supplied to us or retained by the supplier.
When contacted, the suppliers indicated that they had not kept the COC's or CMTR's. Thus, for pipe supports the properties of ASTM-A-36 steel were used l
in the stress analysis. This is a lott strength steel and was commonly used l
industry-wide during the era of Unit I construction.
t The applicable criteria described in our various submittals concerning the show cause effort (IEB 79-07) were used for the analyris effort.
t I
--,e-w-
p-er-r--e,wm-a e
---wa w+ - - - -w-m-e,--
--y--
- - - +wm g--
e----
,e--
w-g<
,---r-
,-mm-
--w-~----o---;
r--,- - - - -,
Besvar Valley Powar Station, Unit No. 1 i
Docket No. 50-334, License No. DPR-66 IE Bulletin 79-14 Page 3 The evaluation of the piping data took two forms. The first was the review of the as-built information versus a Nupipe analysis for piping.
If a new analysis was required, it was performed incorporating the as-built data.
Alternatively, if adequate analytical records did not exist (this was basically for small bore piping), a new analysis was performed. All the piping involved in this effort has been reviewed and, when found unacceptable, all the necessary modifications have been completed.
When evaluating information for pipe supports, a new analysis was perfomned if there was a significant change in the support configuration or if the imposed piping loads increased significantly over that of the latest record.
If neither of the above was the case, the support was determined to be acceptable. Supports were also reviewed to verify that the as-built clearances met their applicable criteria. All the supports within the scope of this effort have been reviewed and, when found unacceptable, all necessary modifications have been completed.
An. analysis of pipe supports located on racks along with their associated local rack attachment effects have been completed and found satisfactory or modification performed. A composite analysis of the rack, which includes the effects associated with non-safety related appurtenances outside the scope of this bulletin, is currently being performed. This analysis will provide a con-sistent, comprehensive analytical basis for these structures..
Nozzle loads on equipment were evaluated in the same way as supports; 3
one difference being that when re-analysis was warranted, the vendors of the equipment were solicited to perform the re-analysis. Because of this, all nozzles have not been completely reviewed by the vendors at this time. The nozzle evaluations to be completed are indicated in Attachment B.
Equipment supports will be evaluated after receipt of nozzle load information from the vendor.
Base plate loads were reviewed to determine if the new loads of record exceeded the plateloads used in the IE Bulletin 79-02 effort.
If the loads were significantly exceeded, a new analysis was performed.
If acceptability could not be justified, then modifications were performed. All the applicable base plates are acceptable for their new design loads. A total of 569 base plates for small bore (generally 3" to 6") piping supports have been evaluated utilizing the IEB 79-02 criteria. As a result, seven modifications were required and have been completed.
Branch lines have been evaluated for flexibility associated with imposed i
movements at the branch connection point for large bore piping. This evaluation il was completed for 105 isometrics involved. Four modifications were required and have been completed.
J l
i w w ww -w w--m---w------e en e w,-www.ier
-v-s-e,as,ay-w-er--www-*-%.ww,s-,-w w-
-wy-ery,.grgm--,m,----wp-s,-w a,---%
=y---,r*-t*,gy----.m
,-y-m--.r--,-e-
--eyec
,-+-*-----++v r,-ws----
Bacvar Vallay Powsr Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 IE Bulletin 79-14 Page 4 As a result of the evaluation described above, the following summarizes the actions performed l
Clearance criteria. modifications (shim plates or member spreading) 345 Existing support modifications (includes 4 branch line mods & 7 baseplate mods) 171 Added supports 32 Maintenance items Ci.e., bolt tightening) 55 Piping changes 0
The final report for IEB 79-14 will be issued upon completion of the nozzle load and equipment support evaluation which we anticipate having complete by July 31, 1981.
Currently, the only condition expected to exceed the final acceptance criteria is associated with the steam line to the turbine driven Auxiliary Feed Pump, W-P2/W-T2. The calculated nozzle load is 304% greater than the allev-able provided by the vendor. The thermal components of the calculated loads are significant and subsequently the calculated loads associated with the interim criteria of the IEB 79-07 task are 56% of the allowable. The piping associated with this condition is planned to be rerouted at the next scheduled outage. The rerouting will alleviate this condition. The turbine pump set has performed satisfactorily in the past under normal operating conditions, thus demonstrating l
that actual stresses during normal operation are significantly lower than calcu-lated.
In viest of these facts, we request that the NRC staff approve the appli-l cation of the Interim Criteria to the auxiliary steam line to the auxiliary I
feed pump turbine drive until the piping is rerouted.
If you have any questions concerning this response, please contact my office.
Very truly yours, hh d..V.Carey Vice President, Nuclear Attachments cc:
Mr. D.A. Beckman, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555 7-m-*-
9 w,-.-y,---,S 9
y,y,-y--
-e y
,we,--.,--------.v.
--,P-w"-Wa--ew--vv.-,=.--v--
t w-*"-*--*mvww---
v----+-we+--
- e-----*---
- - - - - - -=--
]
[
r ATTACHMENT A The following is a report of the percentage of supports and piping geometry that could not be inspected due to high radiation or inaccessibility:
No. of Supp.
No. of Supp.
Analyzed Percent Isos Not Insp.
System Analyzed Not Inpsd.
Not Insed.
For Geometry CC 551 6
14 lt of 55 Iso's QS 103 0
On 10.7% of 6 Iso 's*
RS 133 2
1.5%
5.8% of 6 Iso's*
CE 340 16 54 2.2% of 32 Iso's SI 427 9
24 1.3% of 31 Iso's WR 324 2
1%
7.8% of 41 Iso's**
BR 38 6
164 3% of 5 Iso's All Other Systems 600 0
0 100% of 72 Iso's TOTAL 2,516 41 1.63%
lt of 248 1so's These percentages include large radius circular piping located en the reactor containment dome that could not by physically inspected, however this piping was visually inspected.
l This percentage includes piping located in the intake sump area of the intake structure and was not accessible.
wwy--
--- - -?
r-w-w-
y p-
,-m
%-e
--r-y e-ww--
e--,,---
ww-,e-w-m
, - + -w---g-.--p+wwwep,,-er e--
w-------w--
a
-*-*--a------
ATTACIM4ENT D ST!.TUS OF EQUIPMElff APRIL 2, 19813 13387.02 EQUIPMEfff NAME EQUIP.
NO.
YOTAL NO23I2 NO21LE VENDOR OUF TO VENDOR
- STRUCT, SEISMIC NOZELE STRUCT.
NARE UNITS NO.
IDAD/ALIAM STRESS CONF.
VENDOR RESPole IDADS IDADS IDADS IDAD NO.
NO21IES COMPARED REQ'D.
REQ'D.
Calf.
COMBINEC ACCEPTABIE COOL. RECOV. FLTR.
BR-FL-1A6B 2 7
YES ACCEPT NO NOF REQ'D.
YES YES YES_
Calf. IN CHECEING CESIlm REMOVAL BR-I-A M B 2
4 YES ACCEPT NO NOT REQ'D.
YES YES YES Calf. IN FILTER C1ECKING DEGASIFIER CIRC.
BR-P-7 2
2 YES ACCEPT NO NOF REQ'D.
YES YES YES IN PROCESS PUMP EXCESS LET DOWN CN-E-4 1
2 YES ACCEPT NO NOF REQ'D.
YES YES sJO IAEAT EXCliANGER SEAL NATER FLTR CN-FL-3 1
2 YES ACCEPT NO NOT REQ'D.
YES YES NO CHARGING PUMP CN-P-1A, 1
3 YES ACCEPT NO NOF REQ'D.
NR NR NR NR 18, 1C VOL CONTROL TANE CH-TR-2 1
J YES ACCEPT NO NDT REQ'D.
YES YES YES CALC. IN CHECEING PRIMARY DRAINS DG-TE-1 1
1 YES ACCEPT NO NOF REQ'D.
YES YES YES IN FIIOCESS TRANSFER TANK DIESEL GEN tlEAT EX EE-E-A M B 2
NO ALIDW 10 VENDOR YES IN PROCESS
- NO NR NR NR EMEHG'Y DIESEL GEN EE-EG 162 2
NO ALIDN YO VENDOR YES IN PROCESS
- HO NR NR NR FULL SIZE AUX FN-P2/FW-1 1
YES 1 NOF ACCEPT t YES IN PROCESS
- YES YES YES.
IN PROCLSS FEED PUMP T2 NEUFRON SHLD NS-E-1 1
2 YES ACCEPT YES IN PROCES8*
YES YES NO THE COOL STEAM GEN.
RC-E-!A, 3
5 NO ALIDN YO VENDOR Y,EQ
.IN PitOCESS*
NR NR NR NR (SMALL DORE) 18, 1C DOHON ItLIECT.TNK SI-TK-2 1
1 YES ACCEPT NO NOT REQ'D.
YES YES NO C"3 CONT. let. A/C VS-AS 18, 1
6 NO ALIDW TO VENDOR YES IN PROCESS
- YES NO NO CONT. 304 A/C VS-E-4A, 2
4 YES ACCEPT YES IN PROCESS
- YES YES YES Calf. IN COND.
48
( HECEING SAFETY INJECTION SI-TM-1B 1
1 YES ACCEPT YES IN PROCF.SS YES YES YES YES ACCUMULATOR I4W HEAD SAFETY SI-P-1A,B 2
4 NO ALIDW.
ACCEPT YES IN PROCESS YES YES YES YES INJECTION PUMPS RFrFNERATIVE (NON)
CH-E-2 1
4 YES ACCEPT YES IN PROCESS YES YES YES YES tl EXCHANGER This item w111 pass interim criteria and permisanon is requested to continue operation with the requirement applicable to the interim crateria. See t
information supplied in report.
All nosale loads wl!! be sent to vendor by April 22, 1981.
-