ML20213E449
| ML20213E449 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 06/08/1983 |
| From: | Johnston W Office of Nuclear Reactor Regulation |
| To: | Novak T Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0593, CON-WNP-593 NUDOCS 8306160028 | |
| Download: ML20213E449 (6) | |
Text
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c WN 8 1983 Docket fio. 50-397 f!Cf0RAflDU t FOR: Thomas !!. ffovak, Assistant Director for Licensing Division of Licensing FRCft:
Hilliam V. Johnston, Assistant Director ifaterials, Chemical & Environmental Technology Division of Engineering
SUBJECT:
llPPSS, llASHINGTON fiUCLEAR PROJECT fiO 2, SSER PiPUT -
PRESERVICE ItiSPECTI0t! PROGP.A!' At'D RELIEF P.EOUESTS Plant flane: liashington l!uclear Project tio. 2 (Ut:P-2)
Suppliers: General Electric; Burns & Roe Licensing Stage: CL Docket flo.: 50-397 Pesponsible Dranch and Project !'anager: LG #2; R. Auluck Reviewer: it. R. Hun, (d. F. Cook to B. Brown, IllEL)
Requested Completion Date: June 1,1983 Description of Task: Review of the Preservice Inspection Progrta and Relief Requests Review Status: Applicant's Response Pequired In accordance with a request from the Project !!anager, the Inservice Inspection Section, fiaterials Engineering 3 ranch, Division of Engineering, has reviewed the Preservice Inspection (PSI) Progran and relief recuests submitted by the applicant in a letter dated Pay 3, 1903.
Since a Comission decision regarding issuance of an OL is scheduled for August 1983, the Project lianager requested that we identify all out-standing issues regarding the PSI Progran and subnit an SSER input before June 15, 1933. The resolution of the outstanding issues was discussed on !!ay 13,1983 with the applicant, Project l'anager, MTEB reviewer and COE consultants from IflEL. We have precared the attached recuest for additional infomation (RAI) so that the applicant can provide sufficient infomation for us to complete the review.
Contact:
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306160028 830609 hy 6 ADOCK 05000397 I
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The cutstanding issues are sumarized as follows:
Systen.
The PSI Prngram f or the SD'l systen is not consistent witn the requirenents of 10 CFR 50.55a(g)(2) and Generic Letter 31-35. ;Ie have identified an alternative requirenent in the attached RAI that will provide exanination results equivalent or superior to the requirements of the regulation.
- 2) PSI Delief Reauests.
A) l'epairs due to PSI. Crinding of the surface for inservice inspection resulte.MRHum:bjR.
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.6.a/83 6/...183 pacrow m.io.w w:=c:40 OFFICIAL RECORD COPY
l WASHINGTON PUBLIC POWER SUPPLY SYSTEM WASHINGTON NUCLEAR PROJECT NO. 2 REVIEW OF THE PRESERVICE INSPECTION PROGRAM Inservice Inspection Section Materials Engineering Branch l
1.
Section 6.0 of the WNP-2 Preservice Inspection (PSI) Program Plan (paragraph 6.2) states that Class 2 piping with wall thickness less
)
than or equal to \\" will be examined in accordance with the ASME Code, 1977 Edition, Summer 1978 Addenda.
In Section 7.0 of the WNP-2 PSI Program Plan (Page 7-30) and in letters dated January 13, 1982, March 5, 1982, and April 22, 1983, the Applicant outlined the position that the entire SOV system at WNP-2 should be excluded from preservice and inservice volumetric and/or surface examination.
The Applicant requested a plant specific review based on the Applicant's conclusion that a crack in the piping system would result in con:rol rod in-l sertion and sufficient makeup capacity is available to mitigste the effects of a pipe break.
Generic Letter 81-35 dated August 31, 1981 recommends that the inspection for the SDV system meet the require-l ments for ASME Code Class 2 piping.
l l
- Our review of the SDV isometric drawings in the Applicant's sub-mittals dated September 1,1982 ana February 3,1983 indicates that the SDV system contains approximately 94 welds in piping greater than 4 inches in diameter.
Section XI of the ASME Code requires a surface examination of the SDV systen welds because of the design wall thickness.
It is our position that a preservice examinations of the SDV welcs must be performed based on either (1) the requirement of 10 CFR 50.55a(g)(2) er (2) an approved alternative program in accordance with 10 CFR 50.55a(a)(2).
We have reached the conclusion that an alternative program consisting of a preservice volumetric examination of 10% of the.ASME Ccde Class 2 welds subject to examination would provice supericr results in determining the overall
~
structural integrity of the welds than the Section XI required surface examination of all of the welds.
Provide a discussion of your intentions concerning our position on PSI cIf SDV system piping welds.
f 2.
On page 8 of PSI Program Plan Volume 4, you state tne following; "ISI surface preparations resulted in several hundred cases of mininum wall thickness being violated.
All piping which had.been orepared for ISI has nad the wall thickness of each seld checked.
The result.s of this program were snalyzed by tne Arenitect-Enginesr.
Some of the welds recuired rework which was done by tne Section III piping installatica con-tractor.
All reworked welds were reexamined.'
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- Provide a discussion of the program to examine, analyze and/or repair piping welds that were prepared for inservice inspection and found to be less than the nominal wall thickness.
Confirm that all piping welds determined to have wall thickness less than the design requirements of Section III of the ASME Code were repaired.
l 3.
On page 5 of the PSI Program Plan, Volume 4, you indicate that during l
the mechanized examination of the reactor vessel transducer contact may not have been maintained on the transition from the first to I
second shell course.
Confirm that a manual ultrasonic examination was performed on essentially 100% of this region and that all recordable ultra-sonic indications were dispositioned in accordance with the requirements of Section XI of the ASME Code.
O
s A N 2 0 IS83 DISTRIBUTION:
See attached page Docket No. 50-397 MEMORANDUM FOR:
A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing FROM:
R. Auluck, Project Manager Licensing Branch No. 2, DL
SUBJECT:
FORTHCOMING MEETING WITH WASHINGTON PUBLIC POWER SUPPLY SYSTEM (WPPSS)
DATE & TIME:
July 12 thru 14,1983 9:00 AM LOCATION:
WPPSS Headquarters Richland, Washington PURPOSE:
Caseload Forecast Panel Meeting and Site Visit (Agenda attached)
PARTICIPANTS *:
NRC WPPSS W. Lovelace WPPSS Staff R. Auluck A. Toth A. Schwencer Original signed by R. Auluck, Project Manager Licensing Branch ib. 2 Division of Licensing
Attachment:
Agenda cc w/ attachment:
b 7/ -
See next page SOO705C N 830620
/
PDR ADOCK 05000397 A
- Meetings between NRC technical staff and applicants for licenses are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to "Open Meeting and Statement of NRC Staf Policy", 43 Federal Register 28058, 6/23/78.
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sac ronu sis oo-samacu ovo OFFiClAL RECORD COPY uso m ini-m e
, :.F - E Mr. R. L. Ferguson Managing Director Washington Pubi-ic Power Supply System P. O. Box 968 3000 George Washington Way Richland, Washington 993S2 cc:
Nicholas Reynolds, Esquire Debevoise & Liberman 1200 Seventeenth Street, N. W.
Washington, D. C.
20036 Mr. G. E. Doupe, Esquire Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 Nicholas Lewis, Chairman Energy Facility Site Evaluation Council Mail Stop PY-11 Olympia, Washington 98504 Roger Nelson, licensing Manager Washington Public Power Supply System P.O. Box 968 Richland, Washington 99352 Mr. W. G. Conn, Sr. N/M Group Supervisor Burns and Roe, Incorporated 601 Williams Boulevard Richland, Washington 99352 Mr. Richard Feil U.S. NRC Resident Inspector WPPSS-2 NPS P.O. Box 69 Richland, Washington 99352 Dr. G. D. Bouchey, "anager Nuclear Safety & Regulatory Programs Washington Public Power Supply System P.O. Box 968, MD 650 Richland, Washington 99352
CASELOAD FORECAST PANEL STTE VISIT WASHINGTON PUBLIC POWER SUPPLY SYSTEM PROJECT NO. 2 (WNP-2)
MEETING AGENDA WPPSS Presentation 1.
Overview of project construction and pre:parational testing schedule, including progress and major milestones comoleted, current problems and any anticipated problem areas that may impact the current pro-jected fuel load date.
2.
Detailed review and current status of desien and encineerinc effort (by major ciscioline), including any poten-ial prcbie.ms that may arise from necessary rework..
3.
Detailed review and current status of procurement activities, ircluding valves, pipe, instruments, cable, major corponents, spare parts, etc.
4 Actual and proposed craft work force (by major craft), craft avail-ability, productivity, potential labor negotiations and problems.
5.
Cetailed review and current status of all large and small bore pipe hangers, restrain s, snubbers, etc., including design, ra.,ork, pro-
-curement, fabrication, delivery and installation.
5.
Detailed review of project schedule identifying critical path items, near critical items, amount of ficat for various activities, the current critical path to fuel loading, methods of imolementation of corrective action for any activities with negative fidat, anc provisions for contincencies.
The estimated project percent complete as of June 30,1983.
7 Detailed review and current status of bulk quantities, including current estimated quantities, quantities installed to date, quantities scheduled to date, current percent complete for each, actual versus forecast installation rates, in cubic yards /mo., linear feet /mo., or number /mo., and basis for figures.
(a)
Concrete (CY)
(b)
Process Pipe (LF) f
- Large Bore Pipe (21/2" and larger)
- Small Bore Pipe (2" and smaller) i (c)
Yard Pipe (LF)
(d)
Large Bore Pipe Hangers, Restraints, Snubbers (eal (e)
Small Sore Pipe Hangers, Restraints (ea)
( f)
Cable Tray (LF)
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(g)
Tc tal Conduit (LF) 9 (h)
Tctal Exposed.'4:al Conduit (LF)
(i)
Cable (LF)
- Power
- Control
- Securi ty
- Instrumentation
- Piant Lighting (j)
Terminations (ea)
- Fower
- Control
- Securi ty
- Instrumentation
- Plant Lighting (k)
Electrical Circuits (ea)
- Power
- Contrcl
- Security
~
(1)
Instrumentation (ea)
Detailed review and current status of pre::aration. of preop and acceptance 8.
test procedures, integration of preco and accept.ance test activities with construction schedule, system turnover schedule identifying each system and status, preop and acceptance tests schedule identifying each test and status, current and proposed preep and acceptance tests program canpower.
(a) Total number of procedures required for fuel load.
(b)
Number of draft procedures not started.
(c)
Number of draft procedures being written.
d)
Number of procedures approved.
(e)
Number of procedures in review.
( f)
Total number of preop and acceptance tests required for fuel load identifying each.
(9)
Number of preop and acceptance tests completed identifying each.
(h)
Number of preap and acceptance tests currently in progress identifying each and status.
(i)
Number of systems and/or subsystems turned over to start-up identi fying each.
_ 3 9.
Detailed discussion and status of changes attributed to fiUREG-0737 and other recent licensing requirements.
10.
Discussion of schedular impact, if any, regarding potential deficiencies reported in accordance with 10 CFR 50.55(e).
- 11. Overview of current construction and startup management organization showing interfaces between the two.
- 12. Status of Quality Verification Program.
- 13. Site tour and observation of construction activities.
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JUN 2 01933 MEETING NOT :E 0:STRIBUTION:
Date:
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PRC LB#2 Reading NRC PARTICIPANTS:
E. Hylton Project Manager R. Auluck W. Lovelace H. Denton/E. Case R. Auluck D. Eisenhut/R. Purple A. Toth T. M. Novak*
A. Schwencer S. Youngblood A. Schwencer G. Knighton E. Adensam G. Lainas F. Miraglia J. P. Knight W. Johnston D. Mull er T. Speis R. Houston L. Rubenstein F. Schroeder M. Ernst J. Kramer NRR Division Directors
- OELD Attorney B. Paton E. L. Jordan. DE04: IE J. M. Tayior, DRP : IE Phillips Building Receptionist **
ACRS (16)
Region V
Resident Inspector cc:
Service List
- 0nly if participant in meeting
- 0nly if meeting held in Bethesda
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June 24, 1983
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50-397/460/508 WPPSS MEMORANDUM FOR:
Chief, Document Management Branch, TIDC FROM:
Director, Division of Ruies and Records, ADM
SUBJECT:
REVIEW 0F UTILITY EMERGENCY PLAN DOCUf1ENTATION The Division of Rules and Records.has reviewed the attached document and has determined that it may now be made publicl available.
/ Y
/-
' J.'M. Felton, Director Division of Rules and Records L/
Office of Administration
/
Attachment:
As stated
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2 pI. D men,.. ne. 7 B30624 ji6R'd6 CF05000397 F
REGULATuRf INFORMATION DISTRIbuTZON SYS1-N (RIOS)
ACCESSI0$ NoR:2, :;;m,,
DVC.DATE: 83/04/30 NOTARIZED: NO DOCKET.*
FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Po-e 05000397 50-400 WPPSS Nuclear Project, Unit 1,
nashington Public Powe 050.00460 STN-50-508 APPSS Nuclear Project, Unit 3, nasnington Public 05000508 AUTH uAlE AUTHUR AFFILIATICN eCUCHEY,G.U.
^ashington Puolic Power Supply System HECIP.NAFL RECIPItN1 aFFILIATI0t, te C V A A, T. n.
Assistant Director for Licensing SLBJECT: Central Files version of Rev 3 to emergency preparedness plan consisting of urawings of backup emergency operations facilities at util neadquarters in Richlano,WA.n/830616 Itr.
DISTRIFUTION CODE: x00bS COPIES RECEI%ED:LTR
/ ENCL J2 SIZE:___'I______
TITLE: Emerg Plan (CF Avail)
WOTES:Stancardized Plant. PNL icy FSAR AMDTS & NON PROP REPTS, 05000508 RECIPIENT COPIES RECIPIENT COPIES ID CODE /NAME LTTR ENCL ID CODE /NAME LTTR ENCL NRH L82 BC 1
h 6NRR L84 BC 1
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THA0ANI,M 01 1
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1 AcevtetR/EPB 03 2
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- REG FILES 07 1
1 NOTES 8 1
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O TOTAL NUMBER OF COPIES HEUUIRED: LTTR 15 ENCL
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REVISION 3 APRfL 1933
,e Washington Public Power Supply System 3000 George Washington Way P.O. Box 968 Richland, Washington 99352-0968 (509)372 5000 June 16, 1983 G02-83-529 Director of Nuclear Reactor Regulation Attention: Mr. Thomas H. Novak Assistant Director of Licensing US Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
BACK-UP EMERGENCY OPERATIONS FACILITIES (EOF)
References:
1) letter GD Bouchey to Brian Grimes, " Siting of Emergency Operations Facilities," dated March 20, 1981 2)
Letter GD Bouchey t; Brian Grimes, " Siting of Emergency Operation Facilities," dated December 12, 1980 References 1) and 2) described the Supply System's approacn to responding to NRC requircrLents for near-site emergency operations facilities and requested NRC staff concurrence with this approach. The staff has never responded to the referenced 1etters despite many efforts to obtain staff agreement on this matter.
Nonetheless, the Supply System proceeded in good faith and constructed Emergency Operation Facilities (EOF) close to our generating stations at both our Hanford and Satsop sites in order to provide necessary support during a plant emergency.
At the Hanford site the Emergency Operation Facility (EOF) is 1.3 miles from WNP-1 and 0.75 miles from WNP-2. The Satsop site E0F is 0.85 miles from WNP-3.
In each caso continued EOF habitability has been assured through consideration of site specific accident radiological parameters in the facility.
In view of the radiological protection factors provided by our EOF facilities, we do not believe establishment of provisions for a "back-up" EOF is necessary or appropriate.
However, confirming my telephone discussions with Messrs Tom Novak and R.
Auluck of the NRR staff on June 14-15, 1983, the Supply System will modify our emergency preparedness plans to designate an alternate location for assembly of individuals who would normally respond to the EOF for use in the event that travel in the vicinity of the EOF is hampered by accident radiological conditions. Each alternate assembly location will be equipped with telephone communication links to the respective EOFs and the Plant Technical Support Centers (TSCs).
~
Thomas H. Novak Page 2 Backup Emergency Operation Facilities June 16,1983 The alternate response location for the Hanford Site will be the Supply System headquarters building at 3000 George Washington Way in Richland.
It is 9.5 miles, straight line distance, from both WNP-1 and WNP-2 and approximately 11 miles travel distance by automobile. Existing emergency facilities and communication capabilities at this location are described in detail in the WNP-1/2 Emergency Plan, Rev. 3 and are adequate to accommodate this function. Floor plans of Supply System headquarters building extracted from the Emergency Preparedness Plan (Attachment 1) are provided for your infonnation.
The WNP-3 Emergency Prepardness Plan will be modified to identify the State of Washington Emergency Operation Center as the alternate response location.
It is located in Olympia Washington at a distance 30 miles straight line and 40 miles by automobile from WNP-3. Communication capabilities at this center are described in the WNP-3 Emergency Preparedness Plan, Rev. O and are adequate to accomodate the functions of the alternate EOF response location.
Since WNP-2 is nearing completion we would appreciate prompt resolution of this matter.
Very truly yours,
&W G. D. Bouchey, Manager Nuclear Safety & Regulatory Programs cc:
R. Auluck, NRC E. William, NRC N. Reynolds, D&L D. Chin, Ebasco E. Beckett J. Adams, NESCO D. Smithpeter, BPA A. Vietti, NRC A. Tuzes W. Chin, BPA R. Engelken A. Toth Ebasco - Elma WNP-3 Files - Richland 5
.