ML20213D819
| ML20213D819 | |
| Person / Time | |
|---|---|
| Site: | Columbia |
| Issue date: | 10/06/1981 |
| From: | Rajender Auluck Office of Nuclear Reactor Regulation |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| CON-WNP-0394, CON-WNP-394 NUDOCS 8110140462 | |
| Download: ML20213D819 (7) | |
Text
<
(
I OCT 6 1981 Docket tio. 50-397 l
1 MEMORANDUM FOR:
A. Schwencer, Chief Licensing Branch tio. 2.,DL FROM:
R. Auluck, Project Manager Licensing Branch fio. 2,DDL
SUBJECT:
FORTHCOMING MEETING WITH WASHINGT0fl PUBLIC POWER i
SUPPLY SYSTEM (WPPSS)
DATE & TIME:
Friday, October 9, 1981 I
8:30 AM LOCATI0ft:
G. E. Conference Room
- Bethesda, l
PURPOSE:
Discussion of the Preservice Inspection Program (Agenda Attached) l PARTICIPAN TS:
NRC i
M. Hum, J. Gleim, J. Cook (INEL), R. Auluck WPPSS h
R. Nelson and Support Staff O
ons. a sW
.i I
R. Auluck, Project Manager 1
Licensing Br nch tio. 2 j
Division of Licensing
)
Attachment:
As stated l
..!W,)'c cc: See next page a,/,
. D '4 '
.,/ j r. ~ ;g.
-[, Cl1[/
E! G Y
U \\ v.,,C T e
>1981Q1 W
N Ns
,N4MS*8
/(% %,
M_0140462 811006._ADOCK_05000397 p
l.
e11 i;
en h,
i.
omce >..DL:.L g
.DL:LB l'
tuR~4 c >..Raubniph..Akhwk.ce.r.
OATE )
.. 0/. 6...../B.1....l.Q/. y..../.8.1...
l NRC FORM 318 0480) NRCM O240 OFFlClAL RECORD COPY usam im-sww
(
Mr. R. L. Ferguson Managing Director Washington Public Power Supply System P. O. Box 968 3000 George Washington Way Richland, Washington 99352 ccs: Nicholas Reynolds, Esq.
Debevoise & Liberman 1200 Seventeenth Street, N. W.
Washington,'D. C.
20036 Richard Q. Quigley, Esq.
Washington Public Power Supply System P. O. Box 968 Richland, Washington 99352 I
Nicholas Lewis, Chairman Energy Facility Site Evaluation Council 820 East Fifth Avenue Olympis, Washington 98504 Mr. Albert D. Toth Resident Inspector /WPPSS-2 NPS c/o U.S. Nuclear Regulatory Commission P. O. Box 69 Richland, Washington 99352 Roger Nelson, Licensing Manager Washington Public Power Supply System P. O. Box 968 Richland, Washington 99352 Mr. O. K. Earle, Project Licensing Supervisor Burns and Roe, Incorporated 601 Williams Boulevard Richland, Washington 99352
tenr & J K 2d f'
AGENDA FOR WASHINGTON NUCLEAR PROJECT N0. 2 MEETIfiG October 9,1981 8:30 am to 3:00 pm Participants : NRC - R. Auluck, Project Manager M. R. Hum, Materials Engineering Branch J. Gleim, Materials Engineeirng Branch NRC Consultant - J. F. Cook, EG&G Idaho 1.
Objectives of Review 2.
Overview of Schedule and Status of PSI 3.
Examination Sampling Criteria and Exemptions Based on IWB-1220 and IWC-1220.
4.
Reactor Vessel Examination - Procedures, Resul ts, Areas that are Impractical to Examine, and Regulatory Guide 1.150.
5.
Piping Sys tem Examination - Procedures, Extent of Examination Coverage, Prac-tice with One-Side Access, Practice with Limitations to Examinations, and t
Resul ts.
6.
Relief Requ!sts 7.
Safety Relief Valve Discharge Line 8.
NP.C Ques tions and Discussions l
l 4
A
t
(
WNP-2 PRESERVICE If1SPECTION PROGRAM MEETING TOPICS 1.
For some Class 1 and 2 welds, the WNP-2 preservice inspection plan utilizes Edi-tions and
- Addenda of the Code that are not approved by 10 CFR 50.55(a).
For those cases where examinations have not been performed in accordance with approved ASME Code Editions and Addenda, the application must provide a technical justifi-cation for the use of alternative examinations.
2.
WNP-2 states that remote mechanized ultrasonic examination calibration checks shall be perfonned at intervals not to exceed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> instead of at intervals not to exceed 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> as required by Section XI, I-4230.
Confirm that calibra-tion over the intended 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> calibration interval maintains accuracy and sta-bility as required by I-4230.
3.
WNP-2 states that RHR pump welds are inaccessible.
Is this access limitation only for ultrasonic volumetric examination, or are other examination methods limited also?
4.
WNP-2 states that no ultrasonic examination on Class 2 piping welds (circumfer-ential and longitudinal) with piping walls h inch or less will be performed. This action is not provided for in the 10 CFR 50.55a approved ASME Code,Section XI, 1974 Edition, Summer 1975 Addenda.
The later 1977 Edition up to and including the Summer 1978 Addenda does allow exempting Class 2 piping with walls h inch or less; however, portions of approved editions or addenda may be used provided that all related requirements of the respective editions or addenda are met.
The pre-service and inservice inspection program plan should be modified wherever later 10 CFR 50.55a approved Code editions and addenda are involved to specifically identify the edition and addenda.
5.
WNP-2 states that no ultrasonic examinations will be perfonned on Class 1 piping welds less than 4-inch nominal pipe size.
10 CFR 50.55a has approved the use of the Section XI,1974 Edition up to and including the Summer 1975 Addenda, IWB-1220(b)(1) which states:
"Under the postulated conditions of loss of coolant from the component during normal reactor operation, the reactor can be shut down and cooled down in an orderly manner assuming makeup is pmvided by the reactor coolant makeup system only. However, in no instance may the size exemp-tion be more than 3 in. nominal pipe size."
(
. Additionally, normal makeup systems are those systems that have the capability to maintain reactor coolant inventory under the respective conditions of startup, hot standby, operation or cooldown, using onsite power.
The term onsite power is that power available to the nuclear plant from onsite without any power being supplied from an offsite power distribution system.
The following information concerning piping size exclusions should be provided:
(a) Confinn your calculations for liquid and gasecus fluid piping for which Paragraph IWB-1220(b)(1) exemption is invoked.
(b) List the systems and line sizes that were exempted from preservice exami-nation based on Paragraph IWB-1220(b)(1) of the 1974 Edition including Sunmer 1975 Addenda,Section XI based on nonnal makeup systems using only onsite power.
6.
The WNP-2 preservice inspection program plan does not discuss or define as inspec-table sys tems, the control rod drive cooling water lines common charging and dis-charging headers, and the control rod insert / withdrawal lines.
Identify the ASME
. Code. classification of each of these piping systems and discuss the technical basis for your preservice examination requirements.
j Those piping system lines that are exempted by IWB-1220(b) and which are parallel j
pathed into a common header that is larger in size than allowable by IWB-1220(b) should be identified and the coninon header lines shall be included in the PSI examination program.
7.
WNP-2 has included in the PSI Program, Table 5.2-12, Items B.4.1 and B.4.5, "Exami-nation Area" as follows:
" Safe end-to-piping welds, safe-ends in branch piping welds circumferen-tial and longitudinal welds to include base metal for a distance of is T or 1 inch, whichever is smaller."
l l
The 1974 Edition of Section XI including addenda through Sunmer 1975 cited as the Code being used by WNP-2 requires that base metal examination area include, at
^
least, one-wall thickness beyond the edge of weld.
Discuss the technical basis l
for your decision for selecting the examination area.
l
,.,. - g
( 8.
In Table 5.2-12, Item B-1.4, it is stated that primary nozzle-to-vessel welds and nozzle inner raduis components will be examined from the outside surface. Confi rm that existing procedures and equipment have been qualified on calibration mockups /
standards that enable fatigue cracks to be reliably detected, identified, and characteri zed.
9.
WNP-2 has invoked examination criteria sizing of 2 inches and smaller for category B-G-2 and larger than 2 inches for category B-G-1 as allowed by the 1978 Addenda to the 1977 Edition of the ASME Code,Section XI.
Confirm that all related exami-nation requirements of the 1978 Addenda to the 1977 Edition are being met.
10.
WNP-2 states in the PSI Program Plan sampling limitations as follows:
a.
For Item B6.4, Category B-K-1, " Integrally Welded Supports" and Item 86.5, Category B-K-2, " Support Components" of Table 5.2-12, only valves in Cate-gory B-M-1 will be examined.
It is not the intent of Category B-K-1 and Category B-K-2 to be limited to the sampling of Category B-M-1 of ASME Code,Section XI.
b.
For Item B5.4, Category B-K-1, " Integrally Welded Supports" and Item B5.5, Category B-K-2, " Support Components" of Table 5.2-12, only pumps in Category B-L-1 will be examined.
It is not the intent of Category B-K-1 and Category B-K-2 to be limited to the sampling of Category B-L-1 of ASME Code,Section XI.
c.
For Item B5.9, Category B-G-2, " Pressure Retaining Bolting 2 Inches and Smaller in Diameter" and Item B6.2, Category B-G-1, " Pressure Retaining Bolts and Studs Greater than 2 Inch Diameter" of Table 5.2-12 only pumps l
in Category B-L-1 and valves in Category B-M-1 will be examined.
It is not the intent of Category B-G-2 and Category B-G-1 to be limited to the sampling of Category B-L-1 and Category B-M-1 respectively of the ASME Code,Section XI.
Confirm that all required examinations of the above categories will be performed as part of the PSI Program.
I i
e
ULtJJJ;WJJLE v13oupuuva wu * '
o
=
Docket File (s)
I&E Region i NRC PDR I&E Region II Local PDR I&E Region III Branch Reading File I&E Region IV HSIC I&E Region V TERA NRC
Participants:
TIC E. G. Case D. G. Eisenhut/R. Purple N. Hughes T. Novak S. Varga T. Ippolito R. A. Clark J. F. Stolz (ORB!4)
R. Tedesco B. J. Youngblood A. Schwencer F. Miraglia E. Adensam (LBf4)
J. R. Miller bcc:
Applicant G. Lainas Service List D. M. Crutchfield B. T. Russell Branch Licensing Branch No. 2 J. 01shinski R. H. Vollmer Project Manger R. Auluck R. J. Mattson S. H. Hanauer Licensing Assistant M. Service T. Murley.
J. P. Knight W. Johnston (AD/ Materials & Qualif. Engr}
D. R. f!uller P. S. Check W. E. Kreger L. S. Rubenstein F. Schroeder M. L. Ernst
~'
ACRS (16)
Ol&E (3)
OSD (7)
Attorney, OELD J. LeDoux, I&E V. Moore B. Grimes 9
(
h*-
%h NUCLEAR REGULATORY COMMISSION UNITED STATES 8
W ASHINGTON, D. C. 20555
{
g
%...../
OCT 7 1981 Docket flo. 50-397 MEMORAf0]M FOR:
A. Schwencer, Chief Licensing Branch No. 2, DL FROM:
R. Auluck, Project Manager Licensing Branch No. 2, DL FORTHCOMING MEETING WITH WASHINGTON PUBLIC POWER
SUBJECT:
SUPPLY SYSTEM (WPPSS)
DATE & TIME:
Monday, Tuesday, & Wednesday, October 19, 20, & 21, 1981 9:00 AM LOCATION:
WPPSS Headquarters Richland, Washington Caseload Forecast Panel Meeting and Site Visit PURPOSE:
(See attached agenda)
PARTICIPANTS:
NRC W. Lovelace, R. Auluck WPPSS R. Nelson, et. al.
R. Auluck, Project Manager Licensing Branch No. 2 Division of Licensing l
Attachment:
Agenda cc: See next page j
I f
01i^!"??'" 811007 PDR ADOCK 05000397 PD A
I i
I CASELOAD FORECAST I!,fiEL SITE VISIT MEETIf1G tGEf1DA 1.
Overview of project construction schedule including progress and major milestones completed, current problems and any anticipated problem areas that may impact the current projected fuel load date.
2.
Detailed review and current status of design and engineering effort (by major discipline) including any potential problems that may arise from necessary rework.
3.
Detailed review and current status of procurement activities including valves, pipe, instruments, cable, major components, etc.
4.
Actual and proposed craf t work force (by major craft), craf t availability, productivity, potential labor negotiations and probl ems.
5.
Detailed review and current status of all large and small bore pipe hangers, restraints, snubbers, etc., including design, rework, procurement, fabrication, delivery and installation.
6.
Detailed review of project schedule identifying critical path items, near critical items, amount of float for various activities, the current critical path to fuel loading, methods of implementation of corrective action for any activities with negative float, and provisions for contingencies.
The estimated project percent complete as of September 30, 1981.
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, and basis for figures.
(a) Concrete (CY)
(b); Process Pipe (LF)
- Large Bore Pipe (21/2" and larger) l
- Small Bore Pipe (2" and smaller)
(
(c) Yard Pipe (LF) l l
(d) Large Bore Pipe Hangers, Restraints, Snubbers (ea) l l
L
F
(
(
. (e) Small Bore Pipe Hangers, Restraints (ea)
(f) Cable Tray (LF)
(g) Total Conduit (LF)
(h) Total Exposed Metal Conduit (LF)
(i) Cable (LF)
- Power
- Control
- Security
- Instrumentation
- Plant Lighting (j ) Terminations (ea)
- Power
- Control
- Security Instrumentation
- Plant Lighting (k) Electrical Circuits (ea)
- Power
- Control
- Security (1)
Instrumentation (ea) 8.
Detailed review and current status of preparation of preop and acceptance test procedures, integration of preop and acceptance test activities with construction schedule, system turnover schedule, preop and acceptance tests schedule, current and proposed preop and acceptance tests program manpower.
(a) Total number of procedures required for fuel load.
(b) flumber of draft procedures not started.
(c) flumber of draft procedures being written.
(d) tiumber of procedures approved.
(e) t1 umber of procedures in review.
(f) Total number of preop and acceptance tests required for fuel load.
(g) fiumber of preop and acceptance tests completed.
(h) tiumber of preop and acceptance tests currently in progress.
(i) fiumber of systems turned over to start-up.
[
(
- 9.
Detailed discussion of potential t chedular influence due to changes attributed to (1UREG-0737 end other recent licensing requi remen ts.
10.
Discussion of schedular impact, if any, regarding potential deficiencies reported in accordance with 10 CFR 50.55(e),
11.
Financial commitments to complete the plant,
- 12. Overview of current construction management organization and activities, 13.
Site tour and observation of construction activities.
- 14. Discussion of schedular impact, if any, due to reverification prog ram.
15.
Discussion of schedular impact, if any, due to construction flushing prerequists such as completion of the suppression pool, etc.
- 16. Discussion of Mechanical Contractors Documentation review program as it relate,( to the remaining work scope and any potential schedular impact
l'tLg1MJMU CL.DhbiBUJJM Urut.u J y //aI
(
(
r I
h I&E Region I
!?RCTTft I&E Region II Local PDR I&E Region III Branch Reading File I&E Region IV liSIC I&E Region V TERA TIC f1RC
Participants:
E. G. Case D. G. Eisenhut/R. Purple fl. Hughes
[,' I I
" fx'oh
[x'd'y T. Novak I ( [[I,[ ' ) l'. A, S. Varga f51.u. I t l
\\'m T. Ippolito f(
i GCT 151981* If-J
'. S z (ORBf4)
R. Tedesco 5i u b yt'dT" Sj B. J. Youngblood i,-
/
\\'rh'f[.'s /ff {[$ \\ g A. Schwencer F. Miraglia E. Adensam (LBf4)
J. R. Miller bcc: Applicant G. Lainas Service List D. M. Crutchfield B. T. Russell Branch Licensing Branch No. 2 J. Olshinski R. H. Vollmer Project Manger 2. Oc/ock R. J. Mattson S. H. Hanauer Licensing Assistant M. Service T. Murley.
J. P. Knight W. Johnston (AD/ Materials & Qualif. Engr e
D. R. fluller P. S. Check W. E. Kreger L. S. Rubenstein F. Schroeder M. L. Ernst
~'
ACRS (16)
Ol&E (3)
OSD (7)
Attorney, OELD J. LeDoux, I&E V. Moore B. Grimes
,