U-600399, Forwards Response to SER Outstanding Issue 7ii Re Seismic & Dynamic Qualification of Equipment,Per Sser 5 (NUREG-0853). Responses to Table 3.1 Open Items BOP-6 & NSSS 3.2,9.1 & 9.2 Also Encl for Review
| ML20141M973 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 02/27/1986 |
| From: | Spangenberg F ILLINOIS POWER CO. |
| To: | Butler W Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0853, RTR-NUREG-853 U-600399, NUDOCS 8603030164 | |
| Download: ML20141M973 (50) | |
Text
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U-600399 L30-86 ( 02- 27)-L 1A.120 ILLINDIS POWER COMPANY CLINToN POWER STATION, P.o. BOX 678, CLINTON. ILLINOIS 61727 February 27, 1986
~ Docket No. 50-461
-Director of Nuclear Reactor Regulation Attention: Dr. W. R. Butler, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Clinton Power Station Unit 1 SER Outstanding Issue #711 Seismic and Dynamic Qualification of Equipment
Dear Dr. Butler:
This letter is in response to several unresolved items identified in NUREG-0853 Supplement No. 5 " Safety Evaluation Report related to the operation of Clint:.a Power Station, Unit No. 1." Attached for your Staff's review are responses to Table 3.1 Open Items BOP-6 and NSSS 3.2, 9.1, and 9.2.
Please contact us if you have any questions on this matter.
Sincerely yours, F. A. Spange berg i Manager - Licensing and Safety SMK/cke Attachments (6) cc: B. L. Siegel, NRC Clinton Licensing Project Manager NRC Resident Office Regional Administrator, Region III, USNRC Illinois Department of Nuclear Safety 0603030164 ADOCK O e6 461 %
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Attechr;nt 1 to U-600399 Page 1 to 2 The following equates to NRC SQRT Audit Open Items list of October 10, 1985 and constitutes Illinois Power Company's closeout response:
- Open Item B0P - 6 "The motor (40HP, Frame 364TZ) was not installed."
Response. The installation of the standby liquid control pump motor, IC41-C001, has been completed.
- Open Item NSSS - 3.2 "Some of the pipes attached to the top of the unit (withdrawal lines) were loose."
Response. The subject lines were verified as being properly installed in accordance with RCIC drawings CLN-002, 003, 005, 006, 016 and 100 through 113.
A review of the HCU piping determined the following:
- 1) The lines which serve the HCUs consist of drive water, exhaust, cooling and charging lines. These lines are designed to meet ANSI B31.1 for thermal and deadweight only. Since these lines are non-seismic, they do not have to be laterally restrained.
- 2) The insert, withdraw, and scram drop lines are ASME Class 2 piping. They are designed for seismic loads and are rigidly restrained in all directions.
- 3) Illinois Power Letter G-500039 of December 27, 1985, transmits excerpts from Reactor Controls, Inc. ASME Class 2 piping design reports SA-7458-P i and SA-7458-P-2 for the safety-related riser assemblies of the HCU. These reports demonstrate that the piping to the first fixed points on the HCUs meet ASME code allowables. These reports, along with the General Electric (CE) analysis of the scram riser, satisfy the HCU interface requirements delineated in GE document 23A1906, Section 4. '
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The enclosed IP letter (Attachment 2) and the facts that 1) j the associated HCU piping has been installed as designed, 2) l the HCU piping stresses are within the applicable code allowables, and 3) the piping interfaces meet the HCU requirements (see Attachment 6) should resolve this issue.
- Open Item NSSS - 9.1 "A number of anomalies were observed during the test. GE report 0317HA318 identifies modifications performed l on the switchgear. However, one-to-one correlation between the ;
anomalies and the modifications made to preclude recurrence of ,
similar problems is still missing." i
Attach::nt 1 to U-600399 Pig 2 2 of 2 Response. Quoting from Wyle Report No. 43581-1 on pages 7 and 8 of Seismic Qualification Package SQ-CL683, the anomaly and modification are as follows:
"During test 44 the breaker did not close when the remote control signal was applied. The positive interlock lever wac not in the proper position after the test. Manual tripping of the breaker unblocked the mechanism allowing the breaker to be closed. The General Electric Company made the following evaluation of the problem.
Post seismic testing and analysis by the General Electric Company determined that during Run 44 the breaker mechanism responded properly to the closed signal but could not complete the operation due to blocking by the positive interlock props.
These props were rotated into the blocking position by engagement of the breaker positive interlock roller with its mating cam plate. This was caused by front to back motion of the breaker relating to the equipment...
To prevent the positive interlock parts from blocking a closing operation in the raised connected position, front to back motion restrictors have been added to the design."
General Electric letter IP-2748 of November 11, 1985 (Attachment 3) confirms that the modifications described in Wyle Report No.
43581-1 were incorporated in our equipment. Proprietary drawings of the motion restrictor were audited at General Electric's Philadelphia plant on November 21, 1985. Attachment 6, figure 1 and photographs 1-3, which show the motion restrictor, were taken during the audit. Switchgear installed in Clinton Power Station then were inspected, and puotographs 4-9 show their motion restrictors.
- Open Item NSSS - 9.2 "Nonconformance tags issued by QC (e.g. NCR 32343 and NCMR 2-0054) were observed during site inspection."
Response. NCR 32343 which resolved the unapproved material used on internal jumper wires in the switchgear and NCMR 2-0054 which replaced a lamp socket have been completed and copies are enclosed as Attachments 4 and 5 for your review.
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- N-36-85(12-27)-6 ILLINOIS POWER COMPANY .G-500039 ljjQF HRL-609-85 CLINTON POWER STATION. P.O. 80x 678. CLINTON. ILLINCIS 61727 December 27, 1985 Mr. L. H. Larson General Electric Company 175 Curtner Avenue San Jose, CA 95125
References:
- 1. General Electric Letter IP-1938 dated September 28, 1982.
- 2. General-Electric Document 23A1906, HCU Interface Definition Document.
- 3. General Electric Letter IP-2572, dated March 28, 1985.
Dear Mr. Larson:
Clinton Power Station CRD Hydraulic Control Unit Qualifications As requested in reference 1, Illinois Power Company is trans-mitting excerpts from Reactor Controls, Inc., ASME Class 2 piping design report for the safety-related riser assemblies of the CRD Hydraulic Control Unit. These reports successfully demonstrate that the HCU piping from the interface couplings to the first fixed point on the HCU meet ASME code allowables. The first fixed point on the HCU's have been established as follows:
Insert Riser . . . Inlet Scram Valve (Part 126)
Scram Discharge Riser . . . Check Valve (Part 119)
Withdraw Riser . . . Outlet Scram Valve (Part 127)
Note that GE has performed a special analysis for the scram riser piping between valve 127 and valve 119 (Reference GE Design Memo MDE-550385 previously transmitted to IPC via reference 3).
Based on the above, the interface requirements delineated in GE Document 23A1906, Section 4 have been satisfied. If you have any questions, contact J. M. Munic of my staff.
Sincerely yours, N bK {
H. R. Lane l Director - Design Engineering
. Nuclear Station Engineering Department JMM/slj Enclosure cc: D. C. Shelton, V-928 P. E. Walberg, V-928 P. - Raysircar, V-928 M. Helminski, (S&L Chicago).J[O S. R. Bell, V-390 ;
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Reactor Controls, Inc.
F SAN JOSE, CALIFORNIA TITLE: Design Analysis Report DOCUMENT: SA-7458-P-1 for I/W Piping PREPARER DATE l CHECKER DATE REV PAGE
, CUENT: Baldwin Associates MEK 11/08/85 DHG 11/08/85 0 8
PROJECT: Clinton Power Statior Unit 1 CERTIFICATION 4
The undersigned, a Registered Professional Engineer competent in the field of Piping Stress Analysis, certifies that to the -
best of his knowledge and belief the stress report presented herein for the subject piping system is in compliance with Sargent & Lundy's-Design Specification K-2887 with Amendments 1 through 10 and FECN # 12478, dated 10/08/85 for The Control Rod Drive Hydraulic System of the Clinton Power Station Unit 1 and the ref erenced portions of the ASME Boiler and Pressure Vessel Code,Section III, 1980 Edition with addenda through Winter 1981.
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, SAN JOSE, CALIFORNIA TITLE: Design Analysis Report DOCUMENT: SA-7458-P-1 for I/W Piping PREPARER DATE lCHECKER DATE REV PAGE i CLIENT: Baldwin Associates MEK Ll/08/85 DHG Ll/08/85 0
- 9 PROJECT
- Clinton Power Station Unit 1
1.0 INTRODUCTION
j 1.1 PURPOSE l'
This document constitutes a part of the design j analysis report required by NCA-3250 of the ASME Boiler and Pressure Vessel Code,Section III, for the ~
, Clinton Power Station Unit 1. The purpose of this j document is to demonstrate compliance with Subarticle l NC-3600 of the ASME Boiler and Pressure Vessel Code,
- Section III, and Sargent & Lundy Engineers (S&L) 1 Technical Design Specification for the Control Rod
) Drive Hydraulic System (CRCHS). In addition, this document contains the summary of the results for the Insert / Withdraw Piping.
I 1.2
SUMMARY
OF THE REPORT The report presented herein is comprised of the following:
- 1) A description of all the design input data and criteria used in the analyses of the Insert /
Withdraw lines.
- 2) A summary of the maximum stresses throughout the Insert / Withdraw piping.
l 3) A demonstration that the Insert / Withdraw piping satisfies the requirements set f o rth by the applicable Code and Design Specification.
- 4) A summary of the support loads and interface loads at client specified locations.
1.3 SCOPE This design report covers the Insert / Withdraw piping within the RCI scope of analysis. This includes piping, valves and all fittings from the Control Rod
! Drive (CRD) Housing Flanges to G.E.'s valves 126 and 127 within the CRD Hydraulic Control Units (HCU's).
Reactor Controls, Inc.
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SAN JOSE, CAUFORNIA TITLE: Design Analysis Report DOCUMENT: SA-7458-P-1 for I/W Piping PREPARER DATE l CHECKER DATE REV PAGE CLIENT: Baldwin Associates MEK 11/08/85 DHG 11/08/85 0 37 PROJECT: Clinton Power Statior Unit 1
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8.0 CONCLUSION
)
The Insert and Withdraw piping system within the Reactor C o n t ro ls , Inc. scope of work satisfies the requirements of NC-3600 of the ASME Code, 1980 Edition with Addenda through Winter 19 81 and Sargent & Lundy Engineers Design Specification No. K-2887, including revisions up through
- Amendment 10 and FECN # 12478, dated 10/08/85.
The Insert / Withdraw piping systems also satisfy the functional capability requfrements as specified in Section 3.5.2.
The minimum required pipe wall thickness limits, as defined in NC-3640 of the Code, were satisfied for the >
- Insert / Withdraw piping.
In accordance with NC-3520 of the Code, the Insert /
Withdraw vent valves are qualified since the piping system in which they are located is designed to the requirements of NC-3600 of the Code.
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(~ TITLE: Design Analysis Report DOCUMENT: SA-7458-P-2 l \ for Scram Piping System i PREPARER DATE CHECKER DATE REV PAGE l CLIENT: Baldwin Associates MEK 11/08Z85 J RP _11/08/85 _0_ -
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CERTIFICATION '
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.j i The undersigned, a Registered Professional Engineer competent ;
in the field of Piping Stress Analysis, certifies that to the '
best of his knowledge and belief the stress report presented herein for the subject piping system is in compliance with the
- i Sargent & Lundy Engineers Design Specification No. K-2887 with l l Amendments 1 through 10 and FECN # 12478, dated 10/08/85 for l the Control Rod Drive Hydraulic System for the Clinton Power {
Station Unit 1 and the referenced portions of the ASME Boiler and Pressure Vessel Code,Section III, 1980 Edi tion with j ( Addenda through Wintbr 1981.
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. SAN JOSE, CAUFoRNIA TITLE: Design Analysis Report
'- ( for Scram Piping System DOCUMENT: SA-7458-P-2 PREPARER DATE ICHECKERI DATE REVI PAGE CLIENT: Baldwin Associates MEK _
11/08/85! JRP 11/08/85 0 '
i 12 PROJECT: Clinton Power Station I !
Unit 1 l l 2.2.2 1" Scram Discharge Volume (SDV) Flush Line The }" SDV flush line is attached to the ends ;
of the blind flanges on the Scram Header '
Piping. The portion of this t" line analyzed .
in order to qualify the short flush connection off the SDV end flange, extends from the flange through valves F344 and F345 up to the first support, which is also an acting support -
for the Scram Header. Note that the portion beyond the short flush connection off the SDV flange, was only included in the analysis for a more accurate rep res en tation of the loads and stresses on this short flush connection.
See Figure 2. 2. b.
( The purpose of the 1" SDV flush line is to help flush out any radioactive residue, collected in the Scram Discharge Headers during a scram.
2.2.3 Scram Droos The Scram Drop piping analyzed extends from the sockolet at the Scram Header to the first .
fixed point on the Hyd raulic Control Unit, Valve 114. RCI's scope of supply covers the portion from the sockolet to the interface coupling above this valve. The extended portion of the piping from the interface coupling to the HCU Valve 114 was included and qua1ified in the analysis of the Scram Drops to insure more accurate prediction of the Scram Drop piping response to static Ind dynamic loading.
The purpose of the Scram Drop piping is to 1
discharge displaced water f rom above the drive l pistons during a scram. It also provides a 1
{ path for water flowing to the Scram Header from the CRD seal leakage until the discharge volume pressure equals the reactor vessel pressure.
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Reactor Controls, Inc.
SAN JOSE, CALIFORNIA TITLE: Design Analysis Report for Scram Piping System DOCUMENT: SA-7458-P-2 PREPARERl DATE l CHECKER DATE REV1 PAGE CLIENT: Baldwin Associates MEK 11/08/856 JRP 11/08/85 0
! 49 PROJECT: Clinton Power Station i i Unit 1 l
8.0 CONCLUSION
All components of the Scram Piping System within the Reactor Controls, Inc. scope of analysis satisfy the requirements of NC-3600 of the ASME Code, 1980 Edition with Addenda through Winter 1981 and the Sargent & Lundy Design Specification No. K-2 8 8 7 including revisions up through Amendment 10 and FECN 4 12478, dated 10/08/85. -
The Scram Piping System also satisfy the functional capability requirements as specified in Section 3.5.2.
The minimum required pipe wall t h icicn e s s limits, as defined in NC-3640 of the Code, were satisfied for the
( Scram Piping System.
All in te r f ace loads and valve accelerations for the Scram Piping System are included in this report and have been approved by Sargent & Lundy.
The lug qualification shows that the pipe stresses caused by the rec tangula r welded attachment are acceptable, and that the lug sizes are adequate.
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_ _ _ . - _ . . . . . . . . . _. . i
XEROX TELECOPIE3 295 3 11-12-c5;12:03 PM: 5 5946 + b1226934 2 Facn EuR6 eso; i1.12.1935
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GENERAL $ ELECTRIC NUCLEAA D4ERGY Bus: Ness OPERATIONS l GCNU%L ELECTRIC COMPANY e 175 (URTNER AVEN"JE o SAN Jos!. CAUTORNI A 95125 l
MC 396. (408) 925-3029 l November 11, 1985 IP-2748 L Mr. D. C. Sholton, Manager fluclear Station Engineering Illis is Power Company 500 South 27th Street
. Decatur, IL 62525 Attention: M. E. O' Haem
( Gentlemen
SUBJECT:
CLINTON p0WER STATION, UNIT 1 SQRT AUDIT OPEN ITEMS
Reference:
IP Letter' G-1175, dated September 10, 1985 1 Please find attached the GE input to disposition of a SQRT audit open item as follows:
III. Audit Item NSSS-8: lietal Enclosed Switchgear, MPL No. E22-5004 Open Item 9a: For GE resolution, see the attached GE letter from 1 C. M. Lor.bardo to 0. J. Schmitz, dated flovember 8, l
justification that the field modfrications responding to the Wyle test were incorporated in the equipment design and manufacture. As stated, detail drawings for the seisn'ic motion restrictors are available for audit in the Philadelphia plant of the GE-Dreaker Operation.
This response closes out the referenced letter.
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Mr. D. C. Slowltun Page 2 November 11, 1985 If you have any questions. please contact A. Kanters or myself.
j very truly yours, pa b
L. H. Larson Project Manager Clinton Power Station LHL:csc/I11111 Attachment cc: J. G. Cook H. E. Daniels M. E. D' Haem, w/att W. C. Gerstner J. H. Greene
. D. P. Hall H. R. Lane R. Leong F. A. Spangenberg H. M. Sroka/M. E. Helminskt, w/att D. C. Sh21 ton J. W. Wilsop L
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01NEM. E.104C CCMANY 6M1 IwwCO3 AVEWE
- P*LA3!L elA, PENN9WANIA 19149 * (fl$) 756-f$20 November 6, 1985
Subject:
CLINTON rPCS SWITCH EAR NRC AUDIT OPEN ITEM RESOLUTION BREAKER MOTION RESTRICTOR5 GE REW4 474-68007 '
SUMJtY NO 0269A7303 SHOP ORDER NO 223908 Mr. D. J. Sctrnitz NEtD l . Valley Forge, Pa.
Deat Dant The reference recalsitica teouired that the ecJipment be cesigned ed manufactured with seismic tnotion testrictors described in Wyle Test Report No. 43581-1. This requirement was met.
The motion restrictor details are otovided on the folicwing proprietary drawings wnich sie on file and evallable for audit in the Philadelphia pimt t
. Breeker Dutilne t 016587979 Associated Otawing : 0634D0199 Sheet 4 Steel FisTe Otawing 2 0156 1350 Sheet 155 Please contact tne if you >MC to audit thess atawings.
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- 3. REC'JIREVENTS REcER ENCE(TITLE ,COCllMENT NO. REV., PAR A., SECT., E TC.) PURCHASE ORDER /CATE NSED Review No. 16385 MWR A9427 .
,.g PRRS PR No. PCL 931-83 QCIP 0308-01
- 4. D E SCR;PT.CN OF NONCONcCRMANCE Refer to Pg. 2
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- 7. DISPOSITION O u=E S is O REPAIR S REWORK S REJECT S ENGINEERING LVALU ATION ATTACHEC O CCCUV.ENT REVISION REQUIREC
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- 3. Enginaering Evaluation
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No. PCL 931-83, titled: Pilot Lamp Socket. Dated: 2-2-84, the item was exempt - Ref. NSED Letter Y9498 Paragraph B-4. October 19, 1984, per NSED Form P.1-1, input NSED review No.16385 and NSED Form P.1-3 Pilot Lamp Socket for Equipment No. lE22-S001E revised. Pilot Lamp Socket no longer exempt. NSED justification is, item is non-safety but is a part of a safety component. Due to the reclassification the pilot lamp socket installed per E R A9427 is nonconforming. Note: At the time of installation (2-21-84) pilot lamp socket verified by IPQC for correct part/part number in accordance with applicable draw-ings. F F
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l QUIDES ADDED OTl4ERvilSE SAME A5 0535Do399 SH.*4 f I ~ s ./ , R g
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