ML20237K754
| ML20237K754 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/19/1987 |
| From: | Virgilio M Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20237J194 | List:
|
| References | |
| FOIA-87-87, FOIA-87-A-14 NUDOCS 8708270285 | |
| Download: ML20237K754 (1) | |
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f1EMORANDUM FOR:
File FROM:
Martin J. Virgilio, Chief BWR Assessment Branch Operating Reactors Assessment Staff Office of Nuclear Reactors Regulation
SUBJECT:
REVIEW 0F OIA REPORT 86-10 The purpose of this memo is to document my telephone discussions with T. Westerman, NRC Region IV, conducted during the week of February 9,1987. These discussions i
focused on the content of the travelers utilized to control installation of NAMC0 l
switches at Comanche Peak Steam Electric Station (01A Report 86-10 page 22).
i In response to my request on February 19, 1987 T. Westerman transmitted a copy of the travelers we discussed during the3 telephone conversations. Enclosed, I am providing a copy of the travelers.
l Martin J.
'irgilio, Chief I
l BWR Assessment Branch Operating Reactors Assessment Staff Office of Nuclear Reactor Regalation
Enclosure:
As stated cc w/v enclosure:
D. M. Crutchfield
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l 8708270285 870019' PDR FOIA BAUMAN87-A-14 PDR l
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1-l MEMORANDUM FOR:
Clemens J. Heltemes, Jr., AEOD l
Carl J. Paperiello, Reg. III Robert A. Erickson, NMSS Phillip F. McKee, IE Samuel J. Collins, Reg. I Dennis Crutchfield, NRR Richard Hartfield, IRM FROM:
Guy Arlotto, Chairman Comanche Peak Report Review Group (CPRRG)
SUBJECT:
FOIA 87-87 On January 29, 1987, the Government Accountability Project (G AP) submitted a Freedom of Information Act (FOIA) request to the agency for all NRC records relevant to the CPRRG.
A copy of the request is attached. This FOIA request captures all records in the possession of the NRC related to the CPRRG effort which had been collected or prepared as of January 29, 1987.
Due to the time constraints under which the CPRRG is operating, the agency can, at this time, inform the requestor that the CPRRG is involved in an on-going deliberative process to produce a final report by early April,1987.
For the CPRRG to stop wot k now and process the subject records for release would severely interfere with our work and schedule.
Therefore, the agency will broadly deny the subject record request pursuant to Exemption 5 of the 1
FOIA.
However, to be covered legally on this procedure, it is necessary for l
the agency to preserve the integrity of the records being denied.
This will J
be achievec by archiving all records which fall within the request. NRC i
records are broadly defined (See 10 C.F.R.
S 9.3 afb)) but do not include personal notes not shared with agency personnel and not included in agency files.
Bob Erickson has catalogued the records which the CPRRG has gener-ated or received as a result of its requests for information.
A copy of the catalog is attached listing those records which have been collected or pre-pared up to and including January 29, 1987. These records are being photo-copied and are being stored separately to permit a future response to the FOIA request.
Please review your files and direct those working for you to review their files and identify, photocopy, and archive those agency records which are not listed on the attached catalog but which have been collected or l
prepared by you as a result of your efforts with the CPRRG through January 29, 1987.
Records which are already in the PDR need not be j
Records copied but a notation should be made that they are in you'r files.
ubich are on the catalog but have been marked up or annotated by you should be considered separate agency records and should be archived if they have been shared with others or are in an agency file.
It is anticipated that
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additional NOIA reauests will be forthcoming which will capture all records associated with the CPRRG effo l
)
[
Guy A lotto, Chairraan Coman ' e Peak Report Review Group Attach:nent :
Subject Catalog cc: Linda Robinson, FIPB Edward Shomaker, OGC l
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'l DOCUMENTS RECEIVED BY CPRRG ITEM DESCRIPTION Connelly-to-Zech, et al, 11/26/86,
Subject:
. Allegations t
Memo.
CPRRG-0 of Misconduct by Region IV Management with Respect to the Comanche Peak Steam Electric Station.
(
Enclosure:
01A Report of Investigation with attachments A through PP.)
12/18/86 CPRRG-1 Supplemental sta.tement, Del Norman to G. Mulley Noonan-to-Davis, 1/6/87, w/ attachments (superseded by)
CPRRG-2 Memo.
This is response to CPRRG reouest PG-PO-01 CPRRG-9) _(Note:
Ten CPPO-furnished documents as follows:
CPRRG-3 (1-) Special Review Team Peport
/
(2) Technical Review Team Reports - SSERs, 7, 8, 0, 10, 11 and 13 (3) Comanche Peak Response Team Program Plan and j
3 completed results reports.
(Some of the l
results reports are not yet completed.)
1 (4) TUGC0 Quality Assurance Program Review (5) Cable tray and hanger inspection report (6) HVAC and support inspection report j
(7) CPRT-0A Program Review Report (8) Contention 5 Panel (memo from EDO dated l
2/28/85, superseding earlier memo dated 12/24/84)
(9)
Intimidation Panel (memo from EDO dated 12/24/84%
l (10) Report of Intimidation Panel (letter, FPC to TUGC0 dated 11/4/85)
Parler-to-Commissioners. 12/23/86, Sub.iect: OGC REVIEk!
Memo.
CPRPG-4 0F OTA PEPORT CONCERNING REGION IV MANAGEMENT ACTIO TO COMANCHE PEAK (OI A INVESTIGATION N0. 86-10)
Memo. Connelly-to-Stello, 1/6/87, Sub.iect: DIA COMANCHE PEAK CPRRG-5 (Transmits corrections to chart on page 34 and 35 of REPORT.
basic report, sumarizing Mr. Goldberg's analysis of technical issues.)
IE response (1/9/87) to CPRRG draft request (RG-IE-01)
CPRRG-6 ATTACHMENT 1
DOCUMENTS RECEIVED BY CPRPG CPRRG-7 16 response (1/9/87) to CPRRG draft request (RG-IE-02)
CPRRG-7A NRC Enforcement' Policy 10 CrP Part 2, 49 FR 8583 CPRPG-7B NRC Manual Chapter 4125, Ditfering Professional Opinions CPRRG-7C IE Manual Chapter 0400, Enforcement Program CPRRG-70 IE Manual Chapter 0610, Inspection Reports CPRRG-7E IE Manual Chapter 1245 Inspector Qualifications CPRPG-7F IE Manual Chapter 94300, Status of Plant Peadiness for an Operatina Licensee l
CPRRG-7G IE Manual Chapter 2512, Light Water Reactor Inspection Program -
Construction Phase CPRRG-7H Letter to TUGCO, April 11, 1983, Subjec c.:
CONSTRUCTION APPRAISAL INSPECTION 50-445/83-18; 50-446/83-12 CPRRG-71 Letter to TUGCO, January 21, 1986
Subject:
INSPECTION OF COMANCHE PEAK DESIGN ADFOUACY PROGRAM, SCOPE VALIDATION PROCESS AND REVIEW CHECKLIST DEVELOPMENT 445/85-17, 50-446/85-14 CPRRG-7J Letter to TUGCO, September 9, 1986,
Subject:
INSPECTION OF COMANCHE PEAK DESIGN ADE0VACY PROGRAM (DAP), IMPLEMENTATION OF l
DISCIPLINE SPECIFIC ACTION PLAN (DSAP)X, MECHANICAL SYSTEMS AND COMPONENTS - 50 445/86-18, 50-446/86-15 i
CPRRG-7K Letter to TUGCO, September 10, 1986,
Subject:
INSPECTION OP j
l TERA'S OA PROGRAM FOR THE COMANCHE PEAK DESIGN ADE0VACY 1
l PROGRAM 445/86-17, 50-446/86-14 CPRRG-7L Letter to TUGCO, November 4, 1986,
Subject:
INSPECTION OF COMANCHE PEAK PESIGN ADE0VACY PP0 GRAM IMPLEMENTATION OF SPECITIC ACTION PLANS VIII, IX, and IX; 50-445/86-19, 50-446/86-16 CPRRG-8 RIV response (1/9/87) to CPRPG draft request (RG-RIV-02)
CPRRG-9 Memo.
Noonan-to-Davis,1/13/87, w/ attachments (supersedes CPRRG-2)
(Note:
This is response to CPRRG request RG-PO-01)
CPRRG-10 Memo, Dircks-to-Office Directors, 3/13/84,
Subject:
COMPLETION l
OF OUTSTANDING REGULATORY ACTIONS ON COMANCHE PEAK AND WATERFORD CPRRG-11 Memo. Dircks-to-Office Directors, 10/17/84,
Subject:
COMANCHE PEAK PPCJECT DIRECTCT.
CPRRG-12 Letter to TUGCO, 9/18/84,
Subject:
COMANCHE PEAK REVIEW CPRRG-13 Letter to TUGCO, 11/29/84,
Subject:
COMANCHE PEAK REVIEW CPRRG-14 Letter to TUGCO,1/8/85,
Subject:
COMANCHE PEAK REVIEW 2
ATTACHMENT 1
1
' DOCUMENTS RECEIVED BY CPRRG e
CPRRG-1S Memo. Martin-to-Davis, 1/20/87,
Subject:
REFERENCE MATERIAL l
FOR CPRRG - NOTES OF D. NORMAN i
CPRRG-16 Memo. Marti.n-to-Davis,1/20/87,
Subject:
REFERENCE MATERIAL FOR CPRRG - NOTES OF H. PHILLIPS CPRRG-17 Memo. Martin-to-Davis,1/20/87,
Subject:
REFERENCE MATERIAL FOR CPRRG - REGION IV MANAGEMENT POSITIONS ON ATTACHMENT PF CPRRG-18 Memo.
Martin-to-Davis, 1/20/87,
Subject:
REFERENCE MATERI/.L FOR CPRPG - REGION IV INSPECTION AT COMANCHE PEAK (Note:
This is response to CPRPG draft request--RG-RIV-01)
CPPRG-19 Memo. Martin-to-Davis, 1/22/87,
Subject:
BACXGROUND INFORMA-TION ON CPSES INSPECTION REPORTS CPRRG-20 Memo. Martin-to-Davis, 1/23/87
Subject:
ERRATA REPLACFPENT SHEFTS FOR REGION IV ASSESSMENT OF COMMANCHE PEAR IDENTIF1ED TECHNICAL ISSUES CPRRG-21 Note.
Martin-to-Davis,1/23/87 transmitting amendment to CPRPG-16 CPRRG ADMINISTRATIVE DOCUMENTS 1.
Statement by :hairman Lando W. Zech, Jr., 12/12/86 2.
Memo, Stello-to-Zech, 12/17/86,
Subject:
OIA Report Peview - OIA File 486-10 with enclosures.(including Memo, Martin-to-Stello, 12/17/E6,
Subject:
01A Heport Review:
OIA File 86-10) 3.
Pemo, Zech-to-Stello, 1/15/87,
Subject:
DIA Report Review - 01A File
- 86-10 4.
Memo, Stello-to-Martin, 1/21/'1987,
Subject:
01A Report Review - OIA File
- 86-10 5.
Memo,Stello-to-Doris,1/21/E7,
Subject:
OIA Peport Review:
OTA File
- 86 Establishment of Review Group 3
ATTACHMENT
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llll:::' 'llllllllll Log # TXX-6299 1"""" """:
File # 10115
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WELECTRIC
[.N"S'I'"",',",s.,,
February 19, 1987 I
U. 5. Nuclear Regulatory Commission j
Attn:
Document Control Desk i
Washington, D.C.
20555 SUBJECl:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 REQUEST FOR ADDITIONAL INFORMATION ON OIA REPORT 86-10 j
REGARDING A PIPING SP0OL PIECE REF:
NRC letter from V. S. Noonan to W. G. Counsil dated February 18, 1987.
Gcntlemen:
We have reviewed your letter, referenced above, requesting additional information on a piping spool piece.
We hereby respond t.o the requests for additional information in the attechmert to this letter.
In addition, during the February 17, 1987 telephone call referenced in the above referenced letter, you also reauested the enclosed drawings:
32]OE59 and 1457F27 with Component tiodification Card 4260, Rev. I and Design Change Authorization 15.512, Rev. 8.
Very truly yours, f,
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n n u'i W. G. Counsil
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By:
G. S. Keeliy
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Manager, Nuclear Licensing JDS/ef Attachment Enclosures c - Mr R. D. Martin, Region IV Mr. D. L. Kelley, R1 - Region IV Mr. H. S. Phillips, R1 - Region IV 8702260199 870219
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Attachment to TXX-6299 February 19, 1987 Page 1 of 1 1
Information Request on 0IA Report 66-10 OI A Report 86-10, provided by Board Notification No 86-24 refers on page'5 to an issue " Failure to Properly Identify a Spool Piece." This issue is mentioned again on page 6 and page 9.
Page 9 states "...the utility located a mark on the spool piece and showed it to the inspectors."
If possible, please identify the size of the piping spool piece, the location of the spool piece within the chemical volume control system (CVCS), the type of material (e.g.,
stainless steel), and the_ consequences of a failure of spool piece.
Response
1 The subject spool is located between field weld 1) and 6) on drawing BRP-CS '
RB-076.
The spool consists of 4 pieces:
i Piece 2 - 6' 6-5/16" - 3" Sch. 160, SA 376, Type 304 Piece 6 - is a 45 degree elbow 3" Sch. 160, SA 403 WP 304 Piece 3 - is a 10-3/16" - 3" Sch. 160, SA 376, Type 304 i
Piece 5 is a 90 degree elbow - 3" Sch.160, SA 403 WP 304 The spool is located between valves 2-6085 and 2LCV-460 on the CVCS letdown linc from the suction of No. 3 RC pump.
The spool is Class 1.
This line can be found on drawing 2323-M2-0250 and 2323-M2-0253.
Valve 2-8085 is "open" during normal plant operation.
Therefore, the spool would be part of the RCS pressure boundary.
If the spool failed, a 3" leak would occur within containment.
This size leak is within the analyzed condition for design ' oasis LOCA (postulated line break).
I
Enclosure to TXX-6299 Page 1 of 14 l
Assemble. drawings as shown below.-
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NOTE:
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C E PALLARD 7 C ESSELMAN SUBJECT R eV e SUPPORT MODIFICATIONS MEE-55D-4216 RErl V DRAWING 1457FE7 SPECI AL NOTE E j
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.i PAGE 1 Cr *1 C34Atm FEAK STEAM CICTRIC S'DC'ICH EC5IGN CEANGE ALnsolu2ATICN (WEL) (W2lll$XR7? BE DCCRP0 FATED IN CESIGi CCCDENT CCA tc,16,813 Rev.
1.
SAFE 'T REIATED ECCCNICc: XX TES IC 1.- CRIGIh%;su CPPE XX cpfangi csicNER i
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ur.m.iurdCM See Att uhed List
-REv.
A APPLICAELE SFBlM3Cvo u.m u w THIS REVI'SION VO!DS AND SUPERSEDES DCA 16,'813 Rev, 7.
..B, nmc PROBLEM:. Welding information for attaching shims to the NSSS support / restraints is not well defined.
A SOLUTION:
Revise the drawinos as indicated.
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REVISION 8 As noted.
35-1195 n L v 4 4 V 1 L./
J AN 311985 4.
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DCA-16,813 ROV-8 Page 2 of 3 APPLICABLE DRAWINGS:
1457F27 Rev. 7 1457F30 Rev. 12 1457F31 Rev. 9 1457F33 Rev. 7 1457F34 Ri!v'. 5 1457F36 Rev 4 f
1457F37 Rev. 6 1462F75 Rov. 6 1457F27 1.
Add Hote 14 in " General Hotes" to read as fcilows:
Shim gaps indicated (including zero) shall have an installation tolerance of 40 and
.020".
Shims incy ba sub-divided as needed to obtain the desirec thickness.
Welding information is general.
Specific weld details shall be given on installation documentation.
Shims sufficiently captured do not require welding.
1457F30 2.
Revise Note 4 to read:
"... weld shim to shim and shim to support with 3/16" fillet as specified on installation documentation. Reduce the size of one shim sufficiently to perfonn the welding.
3.
Revise Notes 5 and 6 to read:
... weld shim to shim and shim to support with 3/16" fillets on short sides or 3/16" fillets as specified on installati document.
Reduce the size of one shim : sufficiently to perform the welding.
l'457F31 4.
In Zone C-11 delete field weld symbol and beneath "3-h x 14-1/8" shim plate (4 or 8 if needed) state:
"fiele weld, see 1457F30'.
1_457F33 5.
Revise Note 2 to read: Machine shim bar to 0" clear.snee in hot position.
Ficid weld in slot:
TR-1 Groove weld, TR-2 Fillet weld.
1457F24 ReviseNote3$ read:
"... weld shim to shim and shim to support strut 3
6.
with 3/16" fillets as specified on installation documentation. Reduce the size of ona shim sufficiently to perform the welding.
7.
Revise Note 4 to read:
... weld shim to shim and shim to support strut with 3/16" fillets as specified on installation documentation. Reduce the size of one shim sufficiently to perform the welding. Shims 1/8" or less in thickness shall be attached with full size tacks spaced approximately every 5" all-around.
1457F36 8.
Revise Notes 2 and 3 to read:
... weld with 3/16" fillets, tcp and bottom.
l Rge tv et 'i 4 DCA-16,813'Rev. 8 Page 3 of 3 1
l f
1457F37 4
9.
In view B-B and P-P, change. weld details to.show 3/16" fillets as specified on installation documentation.
1 10.
Revise Note 4 to read:
" Machine in field to 0" clearance in cold position.
Weld shim sets together with 1" long 3/16" fillets centered on two sides.
Weld shim set to saddle with 3/16". fillet one side only.
1457F75 11.
Revise the shim note in View A-A to read as follows:
"... tack weld with 3/16" fillets as specified on installation documentation.
)
i GENERAL NOTE
- 12. Anywhere a specified weld size is called out, and the shim plate is too thin for this size weld, the weld size shall be governed by the shim thickness. Weld length are to be increased to account for reduced-weld sizes.
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UNITED STATES 3 ' 'l i,
NUCLEAR REGULATORY COMMISSION j
}
WASHINGTON, D. C. 20555 o-N;7l;./
MAR 4 1987 HEMORANDUM FOR: Guy A. Arlotto, Chairman Comanche Peak Report Review Group FROM:
Dennis M. Crutchfield, Assistant Director Division of PWR Licensing-8 Office of Nuclear Reactor Regulation
SUBJECT:
REVIEW 0F RECOMMENDATIONS CONTAINED IN THE TASK GROUP 2 REPORT The purpose of this memo is to document Task Group 3's coments on the recommendations provided in the CPRRG Task Group 2' Report, Revision 1, dated March 2, 1987. As discussed in the Task Group 3 Report dated February 27, 1987, we believe that the conclusions reached by the two Groups correlated well with each other. Similarly, as a result of an evaluation of the recommendations, i
we find that the recommendations of the two Groups correlate well with each other. Accordingly, we endorse the recommendations contained in Sections 1.7.1 and 1.7.3 and one of the two recommendations contained in 1.7.6 of the Group 2 Report. We do not support the recommendations contained in Sections 1.7.2 and 1.7.5 and one of the two recommendations contained in Section 1.7.6 of the Group 2 Report at this time primarily because of ongoing applicant prdgrams that should resolve the concerns. Specific comments on each of the recommendations are provided in the enclosure.
We have discussed our comments with the leader of Task Group 2 and he concurs with our proposal for disposition of the Task Group 2 recommendations.
I
/
Dennis M. Crutchfield, Ass stant D rector Division of PWR Licensing /B Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/ encl.:
C. J. lleitemes, Jr.
C. Paperiello J. Lieberman R. Erickson P. McKee S. Collins R. Hartfield fq od g y s
as
)
?
TASK GROUP 3's COMMENTS ON TASK GROUP 2's RECOMMENDATIONS l
1.
Section 1.7.1 of the Task Group 2 Report recommends a review of the applicant's traveler development program to determine how design j
information and design changes were handled. Based on our review of the concerns associated with the reactor pressure vessel installation l
and the NAMC0 switch replacement program, we find broader implications of deficiencies than those stated in OIA 86-10 related to the development and use of travelers at CPSES. Accordingly, we recommend confirmatory i
NRC actions (Task Group 3 Report Section 3.2) and additional applicant actions (Task Group 3 Report Section 3.14) to focus on the adequacy of 4
the traveler program. ' Although less prescriptive than Task Group 2 in discussing acceptable methods for addressing concerns related to the traveler development program, we make a similar recommendation in l
Section 3.14 of the Task Group 3 Report. Accordingly, we support the Task Group 2 recommendation.
i l
2.
Section 1.7.2 of the Task Group 2 Report recomends further NRC review of l
the completeness of QC coverage and technical acceptability of actual l
inspection criteria to compensate for deficiencies in the audits and surveillance at CPSES.
Based on our review of concerns associated with audits and surveillance, we find broader implications of deficiencies than those stated in 0IA 86-10 related to the audit plan for overall i
program assessment. Recognizin ISAP (as discussed in the SSER)g the CPRT Program Plan and the ongoing
, we recommend that NRC monitor the ongoing programs (Task Group 3 Report Section 3.3).
If through these efforts the NRC determines that the applicant's programs are inadequate, additional action such as recommended by Task Group 2 may be required. However, we do not recommend new initiatives, such as those proposed by Task Group 2, at this time.
3.
Section 1.7.3 of the Task Group 2 Report recomends verification of the existence of an adequate material identification and traceability program, and proposes methods for performing this verification. Although less prescriptive in discussing acceptable methods for accomplishing this verification, we make a similar recommendation in Section 3.4 of the Task Group 3 Report. Accordingly, we support the Task Group 2 recommendation.
4.
Section 1.7.4 of the Task Group 2 Report makes no specific recommendation, but discusses a perceived philosophical position at Region IV on records.
We have no specific recommendation on the issue. We note in Section 3.6 of the Task Group 3 Report that neither the B&R procedure nor the ACI Standard recommend documentation of inspection, however, maintaining such records would be prudent.
5.
Section 1.7.5 of the Task Group 2 Report recomends additional NRC review of the CPSES record control program, specifically focused on the applicant's treatment of in-process documents. As discussed in Section 3.7 of the Task Group 3 Report, the applicant has recognized a deficiency in this area and comitted to revise procedures as corrective action. We recomend that as a confirmatory action NRC review this revised procedure to determine if it is adequate to resolve the deficiency. We believe this cpplicant comitment and our recomended NRC action should resolve the concern. Therefore, we find the Group 2 proposed action is not necessary at this time.
a s :
6.
Section 1.7.6 of the Task Group 2 Report recommends a review to determine if the Reg. Guide 1.97 QA commitments have been properly implemented at CPSES and a review of the applicant's program for updating records.
Based on additional review of the FSAR and SSER sections related to' Reg. Guide 1.97, we determined that the NAMC0 switches in question are not within the scope of the Reg. Guide. Therefore, no aoditional review of this issue is required. However, as discussed in Section 3.14 of the Task Group 3 Report, we recommend additional applicants action to' determine the root cause of the record / hardware mismatch. Our recommendation and that of Task Group 2 are quite similar on this issue. Accordingly, we support the recommendation.
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