ML20212N714

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Final Response to FOIA Request.Documents Available in PDR & Encl Include Tw Bishop 811028 Memo,Insp Guidance,Const Schedule,G Spencer 691112 & 1223 Ltrs,J O'Reilly 1970 Ltr to R Boyd & Insp Repts
ML20212N714
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 08/26/1986
From: Grimsley D
NRC OFFICE OF ADMINISTRATION (ADM)
To: Sholly S
MHB TECHNICAL ASSOCIATES
Shared Package
ML20212N718 List:
References
FOIA-86-585 NUDOCS 8608290128
Download: ML20212N714 (2)
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. q)2.-o4, p naog UNITED STATES No NUCLEAR REGULATORY COMMISSION f "

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O W ASHING TON. D. C 205$5 5 i AUG 0 0 G86

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.Mr. Steven C. Shully Ascocinte Connultant M!!B Technical Acacciate:.

1723 Hamilten Avenue, Coit- K IN RESF0N3E REFER San Joce, CA 90120 TO FOIA-86-Se5 Dea r Mr Gholly:

This is in regard t,o your requeat, p u r.s u e n t to the Freedom oi' Information Act, to which the NRC acelened the above number This lo a parti al ret. porose to your reque.s t . We will notify you upon completivn of nearch for and review of any addit.ional records subseet to your request.

X__ The at,aff haa compl e te<; the search for and review of recorde subject L: your request, and this _c the final reaponse to your r eques t.

The NRC hae. no reevras subject tu your requeet.

Records subject to your request. are availSble for pubile inspect.ivn and corying at, the NRC Public Document. Room (PDR), 1727 H Street, NW, Washington, DC 20565, a.., noted on the encionorete). The PDR accesulo's number is identifled beside each record descriptivn.

! . X _. R+ cor'Is subject tv your request are being made available l for p'iblic inupection and copylng at the NRC Public Dveument Room (PDR), 1717 H Street, NW, Washingten, DC 20050, in the PDR file folder under the above number and your name. Th se records are 11cted on th enclosure (u).

We are enelocing 4 n.tice that providee information nbout charcea and prowedur- f or ubt.uning recordt from the PDR.

Sincerely.

/

mso Y YAL A Dennie H . Grimoley , Director D1 vision of Rulem und Boeorda offten of Aelministratten Encl e ure(c)- Ac etrted 8608290120 860026 PDR F01A POR SHOLLYB6-585 s

F01A-86-585 Appendix ITEM A. 10/28/81 Memo for J. L. Crews from T. W. Bishop, subject: Review of NRC: IE Programmatic Inspections for Design During the Period of Diablo Canyon Unit 1 Construction (9 pages)

8. 1. 1968 PI-3800/1 (15 pages)

?. 1973 PI-4000/1 (33 pages)

PI-4000/2 (11 pages)

3. 1975 MC 2511 IE Inspection modules 35003B, 350048, 35016B, and 35018B (141 pages)
4. 1975 IE Inspection Modules 351008 and 35200B (34 piges)
5. 1976 IE Inspection Modules 357448 (18 pages) i 6. 1977 IE Inspection Modules 379908, 379918, 37992B, 37993B, 37994B, 37995B, 37996B and 37997B (66 pages)

- only eight modules on file

7. No recorcs .
8. 9/14/79 TI-2515/29 - Int.pection Raquirements for IEB-79-14 (6 pages)
9. 1980 IE Inspection Modules 370518, 370558 and 35061b (32 pages)
10. 1980 IE Inspection Modules 37700,37701(9pages)

- No record of 37702 C. No Record located D. 1. 02/07/69 ConstructionScheduleatDiabloCanyon(5pages)

2. 11/12/69 Ltr from G. Spencer to J. O'Reilly re: Manag meetipg .,1 at the corporate offices of PG&E (J pages)
3. 12/23/69 Ltr from G. Spencer to J. O'Reilly re: Report on initial QA inspection on December 8-9, 1969 (17 pages)
4. 1970 Ltr from J. O'Reilly to R. Boyd re: Re

- management meeting on 1/6/70 (6 pages) port covering

5. 03/26/70 Inspection Report 323/70-2 (16 pages)
6. 05/07/70 Inspection Report 323/70 4 (21 pages)
7. 09/30/70 Inspection Report 323/70-2 (6 pages)
8. 12/1/70 Irspect' ion Report 275/70-5 (17 pages)

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[i, j F) g, OCT 2 81981 \ ,

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MMORANDLM FOR:

J. L. Crews. Director. Division of Resident.

Reactor Projects and Engineering Inspection THRU: B. H. Faulkenberry, Chief. Reactor Construction l Projects Branch

FROM
T. W. Bishop. Chief. Reactor Projects Section 1

SUBJECT:

REVIEW 0F EC:IE PROGRAMATIC INSPECTIONS FOR DESIGN DURING THE PERIOD OF DIABLO CANYON IMIT 1 CONSTRUCTION I Diablo Canyon Unit 1 Construction Permit was issued in April 1968 with i

construction effectively underway in 1969. The information provided below is a sinuary of the IE program mquirements relating to inspections i of design activities and includes quantitative data on inspections perforwed. The information was compiled from seterial availible from ,

IE:RV files.

_ Pre-1968:

t

' Requirements for pre-CP design-related inspections could not be reconstructed from information available in the Regional Office.

i However, based upon information contained ivi later inspection instructions (PI-3800.1968), it does not appear that significant design-related inspectior.s were required.

i l'368-1975: ,

!' During this time frame, inspections were performed under PI-3800 '

and PI-4000. PI-4000 could not be reconstructed from Regional i

files, but, from references to PI-4000 it appears that the inspection l

guidance centered on verifying that a QA program had been established.

PI-3800, paragraph F.3 contained some specific guidance regarding

! Design Review

,c i

" Design Review t

j ii This is an area for which the Compliance inspection program is currently limited to a determination as to whether the i

i licensee has a system for the independent review of design as ,

part of his QA program. Possible deficiencies in design may

3i be detected during the course of nautine Compliance inspection; ,

i:

j,

[L but, at present, design is not spot-checked or reviewed as part of the Compliance function. When possible design deficiencios '

i i Ry are found, they are referred to DRL for appropriate action." ))

TWBishop:nn Faulkenberry j g g@ (L w 7,f- r -[ l j- In/ /A1 . 10/ /A1 .
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.o J. L. Crews 4 Based upon this PI. it appea'rs that the program was limited to i verifying that an independent review system was established. The i PI-3800 program did not make any other specific references to i design type inspections. ,

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i In 1973 a TI-4000 series was' issued. This series did include some i' requirement for inspecting design controls, but the TI also contained an applicability etetement. This statement required the TI to be performed on plants whose construction pemit application was dated after September 1. 1973. This TI was, therefore, not applicable to Diablo (CP issued April 1968).

! During the 1968-1975' (inclusive) time frame our files indicate l six inspections were perfemed which reference some specific j inspection of design control (Report Nos. 69-04. 70-01, 70-02

! 75-07, 75-11 and 75-14). These inspections included progranuatic reviews and followup on some specific design changes.

i 1975-Present i

i In 1975 the IE redule system was issued. Design-related inspections were specified in four MC 2511 series modules (35003, 35004. 35016

and 35018). These modules were issued in May 1975 and were identified, i for use on Pre-CP inspections (again. Diablo could have been excluded i frominspectiontmderthesemodules).

I In 1975 Diablo Canyon Unit was heavily involved pre-operational

! testing. Construction was considered to be apprcaching completion l (although the HDSGRI issue us lingering). The MC 2512 modules, j issued originally in March and May 1975, relating to QA reviews 1 (35100 and 35200) included some refincd instructions on inspecting design controls, but were not considered applicable since Diablo i

construction was so advanced. ,,

4

! In October 1976 under MC 2514 (Pre-ops) a module was issued relating 1

to design changes and modifications (35744). This module was performedfor Diablo Unit 1 and is documented in report No. 77-15 (as 905 complete).

)

i In August 1977 the NRC issued a series of nine modules (37900's) i specifically relating to design to be administered under the LCVIP program. These modules were never applied to Diablo Canyon since' I PG&E was their own A/E and was not inspected under the LCVIP.

In 1977 the inspection requirements for the HOSGRI modifications were defined by Region V (Kirsch /Vorderbrueggen memorandia to Spencer, dated December 20.1977). While no specific modules were identified it was state.d that design control, review, verification, and documentation would be inspected. IE Inspection Reports fur ..

Diablo Unit 1 indicate inspections of this nature were performed * '

(Nas. 78-01, 79-01. 79-06. 79-23, 80-02, 80-06. and 80-10). 766 infomation shows that these inspections were perfomed using the 92700 series modules (followups) and TI-2515/29 (IE8 79-14 followup). '

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'. J. L. Crews In 1980 three new MC 2512 modules were issued which required some design inspections (37051, 37055, and ,35061). These modules were not applied to Diablo Canyon Unit I since construction was essentially complete at this time.

AlsoinOctober1980,threeMC2515(operationsphase) modules were issued which related to design (37700. 37701. 37702). These inspections have not yet been performed at Diablo Canyon Unit 1 since the operating license was just recently issued.

During the post 1975-present time period, our files indicate ten inspections were performed which reference some specific inspection of design control (Report Nos. 77-12. 77-15, 78-01, 79-01. 79-06 79-23, 80-02, 80-06, 80-10 and 81-10). These inspections included progrannatic reviews and followup on specific design issues.

IA]

(, T. W. Bishop. Chief Reactor Projects Section 1 O

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    1. ' pu a n.,"o I.8NITED STATES
  • g 8*' n NUCLEAR REGULATORY COMMISSION

$ ,E REGION V q 1990 N. CALIFORNIA 80ULEVARD f ".

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[g SulTE 202, WALNUT CRE EK PLAZA WALNUT CREEK, CALIFORNIA 94596 l

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l September 30, 1981 MEMORANDUM FOR: E. L. Jordan, Deputy Director, Division of Resident, and Regional Reactor Inspection l FROM: B. H. Faulkenberr'y, Chief, Reactor Construction l Projects Branch l

SUBJECT:

RESULTS OF REVIEW 0F SEISMIC RELATED INSPECTION ACTIVITIES AT DIABLO CANYON 1/2 In accordance with our telephone conversation on September 29, 1981, Region V reviewed all documentation covering seismic related inspection activities performed at Diablo Canyon Units 1 and 2 since January 1978.

Enclosure 1 provides a listing of all the IE inspection reports, including paragraph numbers, that address seismic inspection activities. The inspection reports that document design area inspections are listed l

/ in paragraph A. Paragraph B provides a listing of the inspection reports covering hardware and QA type inspections. '

(

Enclosure 2 provides the results of our review of the documentation covering the implementation cf inspection requirements contained in TI 2515/29. As described in 1?e enebsure, there are six inspection action statements that the inspt;.uior, documentation does not specifir. ally address as having been performed. It is our belief that these action items were inspected; however, the style in which the reports were written was not adequate to allow identification of, each TI inspection action item.

As reported to you by telephone on September 28, 1981, inspection reports numbered 50-275/79-23, 80-02, and 80-10 document the inspection activities related to IEB 79-14. Inspection Report 80-10 covers the closcout inspection of IEB 79-14 for Diablo Canyon Unit 1.

l udbb D. H. Faulkenber y, b Reactor Construc on Projects Branch

Enclosures:

i As stated cc: J. L. Crews RV f.

1/haf Y9!

ENCLOSURE 1 Region V Inspections Relating to Seismic Issues Performed At Diablo Canyon 1/2 (January 1978 - September 1981)

Reference:

1E:RV Kirsch /Vorderbrueggen Memo to G. S. Spencer Dated 12/20/77 (Attached)

A. Design Activity Inspections 1.~ 50-275/323/78-01 (Par. 3)

2. 50-275/323/79-01 (Par.11, as-built drwg.)
3. 50-275/79-23 (Par. 3)
4. 50-275/79-06 (item #02) 323/79-04 (item #02)
5. 50-275/80-02 (Par. 5)
6. 50-275/80-06; 323/80-03 (Par. 5 drawings review; 9 shsmic

( 7.

8.

interactions) 50-275/80-10; 323/80-06 (Par. 5) 50-275/81-10 (Par 2a, 2b)

B. Hardware M J ta11ations and QA Inspections

1. 50-275/78-02 (Par. 5, 6, 7)
2. 50-275/78-03 (Par. 2, 3, 5, 6, 9,10)
3. 50-275/78-05/323/78-06 (all)
4. 50-275/78-09/323/78-09 (all)
5. 50-275/323/78-10 (all)
6. 50-275/323/78-21 (Par. 2, 3.b. 4, 5, 6, 7, 8, 9,11)
7. 50-275/323/78-15 (Par. d.b. 6, 7, 8,11,12,13,15,16)
8. 50-275/323/79 01 (Par. 2, Sa , b, d, e, g, 8,9,10,12)
9. 50-275/79-06; 323/79 allegations of poor construction quality
10. 50-275/79-07; 323/79-05 (Par. 3, 5, 6, 11, 13)
11. 50-275/79-12; 323/79-07 (Par. 4a 7,10,11) 12, 50-275/79-13; 323/79-08) Par. 3a . b , 4a b , 5, 7, 8, 9,10)
13. 50-275/79-17; 323/79-09 (Par. 2, 4 abc, 6b, 8, 9)
14. 50-275/79-19 (Par. 2)

_ _o

2-( 15. 50-275/79-22; 323/79-12 (Par. 2, 3a, 5, 6, 7)

16. 50-275/79-23 (Par. 3)
17. 50-275/79-26, 323/79-13 (Par. 2.b, 4a, 4c, 5, 6, 7) 18, 50-275/80-02; 323/80-01 (Par. 2.b, 4, 5, 8)
19. 50-275/80-06; 323/80-03 (Par. 5, 6, 9)
20. 50-275/80-10; 323/80-06 (Par. 3, 5, 7) 21, 50-2/5/80-15; 323/80-08 (Par. 2, 3. 4a , 7, 8,10,11)
22. 50-275/80-22; 323/80-11 (Par. 3b, 4a. 5)
23. 50-275/81-04; 323/81-04 (Par. 3b, 3c)
24. 50-275/81-17; 323/81-11 (Par. 3d) e O

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EflCLOSURE 2 -

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RESULTS OF :.EGION V REVIEW 0F INSPECTI0t1 DOCUMEl1TATION .Jh 1b(lW" efJ o Opg COVERING THE IMPLEMENTATION OF TI 2515/29 (TI For IEB 79-14) .

A review of TI 2515/29 inspection requirements and documentation of the inspections (provided in IE Inspection Reports 50-275/79-23,

/80-02, and /80-10) identified the following TI action statements i which are not clearly documented as having been performed:

TI ACTION STATEMENT COMMENT

1. (IV.1) " Review the organization... (no specific reference - but PG&E's who developed the inspection organization was previously reviewed by elements." the NRC and is documented in IE Inspection Reports prior to January 1978)
2. (IV.1) " Interview one of those persons (no specific discussion of an interview -

if available on site." but Braff's name does appear under

' individuals contacted' in the report which discusses the inspection walkdown)

3. (IV.1) "If documentation of the seismic .(no' specific' reference-butReport analysis is available at the site, 79-23 does discuss PG&E's and their inspect it in conjunction with the consultant's actions to relate the seismic documentation of inspection analysis to isometric drawings) elements to determine that pertinent parameters and values '

[( were identified as required by item 1 of the Bulletin."

4. (IV.1) "Also determine, to the extent (no specific reference - although this possible, that acceptance criteria may be inferred since the inspector were developed in a rational reviewe'l the licensee's ' actions' and way." found them acceptable)
5. (JV.1) " Inspections covering the area (no specific reference. May be described above will also be addressed in separate IE:RIV reports) conducted within the organi-zation of three architect engineers. Selection...will be coordinated with the Vendor Inspection Branch by Technical Programs / Headquarter *,."

6.(IV.4.0)"forsiteswherenonconformances (no specific reference - discussion is are identified, assure that provided which states the licensee has necessary improvements tt, quality an acceptable system for resolution assurance procedures related to of discrepancies identified by the design changes due to modifica- inspection. Changes to quality tions or maintenance are com- procedures are not specifically pleted within 120 days of the addre ssed. )

date of the Bulletin."

,

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