ML20087A108
| ML20087A108 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/18/1968 |
| From: | Robert Carlson US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Moseley N US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20086U000 | List:
|
| References | |
| FOIA-95-36 NUDOCS 9508040175 | |
| Download: ML20087A108 (3) | |
Text
{{#Wiki_filter:r-h~E.: i . - - - ~ +f - 9.q: wgu ) j d j-wo. w_ 1 UNITED STATES GOVERNMENT-g,,,,,,g,, l ,4,- - ' To-N. C. Moseley, Senior Reactor Inspector DATE: March 18, 1968,, .{ jl i, +. ~ Region I,-Division of Compliarce i YMrmou : R. T. Carlson, Reactor Inspector 7 l Region I, Division of Compliance susJacr* JERSEY CENTRAL POWER & LIGHT COMPANY g g gg CO. REPORT.NO. 219/68-1 e 9 4,._- } i Attached'is the' report covering inspection activities from f mid-November 1967 through February 6, 1968. Included are the transmittal memoranda from the inspectors-involved. As you are aware, the detailed results of the efforts of the task . e i t force on quality assurance will be covered in a separate report. t The items of major interest as of the last visit covered by this report are reflected in the summary. The status of the principal outstanding issues were reviewed with Messrs. l J McCluskey and Willett during a visit on February 29 - March 1, 1968. The significant results follow: 1 4 1. -Quality Assurance l I i GE has initiated action.in a number of the areas high-lighted during the January 26 meeting. However, no action. l is indicated thus far regarding the expressed need for ? i further assurances of a quality product. During a joint j meeting with McCluskey and Willett, I reiterated our position as follows: ijQ;} a. Cleanup of the specific areas identified was expected, ~ but this alone was not enough. l i b. CO was not, geared to do the job alone. Therefore, i it was up to them. w. .~ ~ ( c. Until further assurances of a quality product are provided, CO will not be able to arrive at a. finding- ,7 l ' y'\\ of satisfactory completion. l , l -a Neither McCluskey nor Willett would commit themselves } ] beyond a "We'll think about it" position. t e J.. .. :.4 N t ~ I a T1 c. vAur bed Negularly on the Payroll Serings Plan 9500040175 950227 = - - - l PDR FOIA DEKOK95-36 PDR.. -
mm. l1-4 s x z. w..., p y y ~ , j-i ) 9( 1 2-3 . i ) - 2.. Preoperational Testing,-Core Loading and'Startup Testing: ,l -{ GE-JC are reviewing ~.this. materia 1.in> light of our comments , "T 'during the January 30 meeting. They expect to have re u v vised drafts' of-some of the material available for review i by mid-March. { M t: 3.- Reactor-Pressure Vessel-Internals' j-T Afte'r considerable discussion, Willett-finally stated l that all of the Avery produced components would be 100% - l inspected and made to' conform with the specifications ~ throughout. I have some reservations,regarding his' . holding to this commitment in the' case of the steam-separator - shroud head assembly, but will wait and see. A team of GE-San Jose andL Avery people was due in at the j ~ site on March 4 to begin detailed inspections. l 4. Control Rod Drive Hydraulic system Penetrations-GE's position is that they have no problem at Oyster Creek.- This is based on a verbal report (to them) from CB&I shops j 3 ^ confirming fabrication to specs combined with satisfactory completion of field hydros. They did agree.to inspect for-undercutting but otherwise plan no further _ action at. present. i 5. Containment penetration Inserts-to-Shell Field Welds GE is following this situation closely but plans to.do ] l-M nothing pending instructions - from San Jose. They're:of the opinion that there is no^ problem at. Oyster Creek. 1 The basis is that the material is different and the Oyster, creek vessel was fabricated under more favorable: conditions, from May 1 - October 4, 1965. j i 6. Rebar Splices 1 l .\\ Early indications are that GE-B&R will not be able to make available all the documentation requested regarding qualification of splice procedures and welders, and that providing assurance of quality production splices. Con-sequently, I may have some problems here. f-r e- =s- ~s e ww w y s,e. e m-v .e wms, y
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w ... ~.. W~ ~ l ~ - - "~ m-N e w M g,, h 7. Status of' Pressure vessel' Problems. a n ;.; The status; as: of February 29,31968 was as follows:: Q [sy F.L s 1], "a. Stub tube field welds! removed 70 .t I b. Control, rod drive housings removed 11, 4, wp. ,c. Stub tube contour grinding completed - 5 g".. d. 'In-core-field welds repairedJ-O. (Waiting on com ! -pletion of removal of drive housings'to' provide accessibility.) a t Each of the areas discussed above will be followed closely. In that regard, am planning the next visit'for mid-March.to coincide with the expected availability ofjthe revised drafts of their preoperational testing, loading and startup-testing i procedures. They also' promised to have ava11hble pertinent documentation-on the control ~ rod drive penetrations.and. rebar splices. .F. Nolan, J.-Collins and possibly R.: Gilbert 4 also plan to accompany me for at least part of the time. As a matter of interest, J. Varela's conclusion regarding-our. joint review of concrete quality assurance was that the work - is above average and exceeds-design requirements. Jersey Central has an amergency. procedure covering loss.of. irestrument air, Procedure No. 503 " Instrument Air Failure" t tJ. O'Reilly memo dated 2/14/68).. A copy is available for I transmittal to CO:HQ.
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w m ,,_,__,._,,,y g ~a ~ -:: r_ :..p .~ ] .g{f J. P.; O'Reilly, Chief, Reactor Inspection & March 18, 1968 Enforcemen Br ch, Division of Compliance, HQ j w l h ey, nior Reactor Inspector { Region.I, Division of Compliance ./ JERSEY CENTRAL' POWER & LIGHT COMPANY ? "7 DOCKET NO. 50-219 m. .j .( j The attached report by our field inspectors of vis'its to the subject facility on November 14-16, 17, ' 20 and 21, 1967; y
- F December 7, 13, 14, 18, 19, 28 and 29, 1967 ; January 9-11, 26 and 30, 1968; and February 5-6, 1968, is forwarded for informa-(
tion. It is noted-that. detailed coverage of the reactor vessel stub tube problem, _and the results of the quality assurance team inspections will be provided in other reports. tg 1 h Since the last visit covered by this report, some progress has F been made in most of the specific items discussed in Addendum I I and II, except the following: ~,
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Additional Quality Assurance
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'b. [ Both GE and Jersey Central indicate that they understand [ that we'are looking for more depth.in their review of the l [ overall plant quality assurance program. At this time, ' however, no definite commitments have been made by either P i A ', company regarding the scope'and depth of the additional effort. If our efforts in the next week are unsuccessful l in getting a definite commitment ~for this program, we plan
- p to have another meeting with top management.
l I ...k 2. Control Rod Hydraulic Penetrations W T 'Ihe GE-Jersey Central position concerning the' possible _[ problems with the control rod hydraulic penetrations is j
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that the hydrostatic test proved the integrity of the 'y system. We have scheduled a visit to the site'on March.18, j d 1968 for our consultant, Mr. Collins, to review this area in more depth. j v. i 0by l ~ ~ w_ mm
~ ,i . L. u- _A ~ ~ .i -h q q s y I We have been told by Mr. Willett, GE, that.all of the core internals made by the P. F. Avery Company will be 100% inspected ~ for conformance with the specifications. We- +} -intend to continue giving attention to this problem. Our review of the plant operating procedures has been delayed because of the unavailability of the procedures - [ for-review. We expect, however, to review all of them i ?!' that are available in the near future and to include ) comments in the next inspection report. It is noted that initial core loading is presently scheduled-i 9 for September 1968.
Attachment:
CO Rpt No. 219/68-1 by R. T. Carlson, et al dtd 3/12/68 c c :- E. G. Case, DRS R. S. Boyd, DRL (2) f S. Levine, DRL (4) D. J. Skovholt, DRL (3) L. Kornblith, Jr., CO Regional Directors, CO I REG files i s l 0}}