ML17214A644
| ML17214A644 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 01/11/1984 |
| From: | Williams J Florida Power & Light Co |
| To: | John Miller Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17214A645 | List: |
| References | |
| L-84-1, NUDOCS 8401130159 | |
| Download: ML17214A644 (10) | |
Text
a REGULATOR)
'4FORMATION DISTRIBUTION S
'EM (RIDS)
ACCESSION NBR:8401130159 DOC, DATE: 84/01/11 NOTARIZED!
NO FACIL:50-335 St. Lucie Plant< Unit 1i Florida Power 8 Light Co.,
"AUTH~ NAME AUTHOR AFF ILIA~~
HILLIAMSiJ ~ 'ji ~
Florida Power R Light Co ~
RECIP,NAME RECIPIENT AFFILIATION MILLER'
~ R ~
Operating Reactors Branch 3
SUBJECT:
Forwards proprietary draft "Integrity 8 Stability of Internals Conclusions L Findingsi" per 830419 8
1214 commitments in response to NRC 830426 request,Rept withheld (ref 10CFR9.5(4)),
DISTRIBUTION CODE:
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SIZEQ TITLE: Proprietary Review'Distribution-Operating Reactor NOTES:
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BOX 14000, JUNO BEACH, FL 3340B FLORIDAPOWER 5 LIGHT COMPANY January I I, I 984 L I Office of Nuclear Reactor Regulation Attention:
Mr. James R. Miller,Chief Operating Reactors Branch N3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Miller:
Re:
St. Lucie Unit I
Docket No. 50-335 Reactor Vessel Internals and Thermal Shield; P lant Recovery Program-Draft lnte ri and Stabilit of'InteTnals Re rt - Conclusions and Findin s
Our letters of April I 9, I 983 (L-83-230) and December I 4, I 983 (L-83-582), committed to provide a report on "Integrity and Stability of Internals - Conclusions and Findings" (Items D.5 and D.6 from our L-83-230) pursuant to the St. Lucie Unit I P lant Recovery Program, the week of January 9,
l 984.
The subject report is herein provided in draft form in order that your review be expedited.
Since our letter of October 25, l 983 (L-83-53I) forwarded the draft Chapter 7 (Failure Mechanism Analysis), of the sane subject report, it is not included in this transmittal.
The documentation herein contained, satisfies items D.5 and D.6 of our L-83-230, and completes all commitments requested in your letter of April 26, I 983.
As has been our positicn since our meetings with you in April l983, and so expressed at that time, return to power is being pursued under IO CFR 50.59.
Portions of Attachment 4 of this letter contain proprietary information, pursuant to the'rovisions of 10 CFR 9.5(4),
as discussed in Attachment I
(Combustion Engineering, Inc., Statement for Withholding from Public Disclosure Pursuant to IO CFR 9.5 (4)).
Since Attachment 4
is being provided in draft form, a detailed delineation of proprietary material has not been made.
Such delineation will be made when the report is reviewed prior to issuance of the final document.
Combustion Engineering has therefore requested that Attachment 4 be returned upon receipt of the final version of the Final Report on the St. Lucie Post-Cycle 5 Plant Recovery Program.
Attachment 2 of this letter contains a "Statement of Clarification Concerning Draft Final Report Content", since core support barrel repair is still underway.
Attachment 3
describes Quality Assurance program activities undergone during the recovery operation.
Completed items/tasks integral to the St. Lucie Unit I Plant Recovery Program are as follows:
840ii30i59 840iii PDR ADOCK'05000335 P
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Page 2 Office of Nuclear Reactor Regulation Mr. James R. Miller,Chief U. S. Nuclear Regulatory Commission L-83-230 Action Items Letter (NA)
INITIALASSESSMENT QF REACTOR VESSEL INTERNALS Date L-83-230 4/19/83 (4/I 2/83 NRC Meeting)
(Dl)
REACTOR VESSEL INTERACTIONS (PTS) L-83-263 4/27/83 (C)
RECOVERY PLAN L-83-264 4/27/83 (4/25/83 NRC Meeting)
(D2)
EFFECTS ON FUEL PERFORMANCE L-83-265 4/27/83 (NA)
(D3/D4)
(NA)
(NA)
(NA)
(A)
(NA)
LPMS ANDEXCORE DETECTOR DATA REVIEW/RECOVERY PLAN REVISION RV GAMMAMATINGSUBMITTAL EXXON RELOAD SUBMITTAL FINALEXXON RELOAD SUBMITTAL REACTOR VESSEL INTERNALS AND INSPECTION RESULTS/RECOVERY PLAN REVISION RECOVERY PLAN REVISION L-83-345 L-83-367 L-83-369 L-83-429 L-83-452 L-83-475 6/7/83 (6/3/83 NRC Meeting) 6/23/83 6/23/83 7/27/83 8/22/83 (8/I 6/83 NRC Meeting) 9/7/83 TECHNICAL SPECIFI CATION P/T LIMITS L-83-280 5/3/83 (NA)
(NA)
POST-LUG REMOVALFINAL NCE INSPECTION RESULTS RECOVERY PLAN REVISION L-83-509 I 0/6/83 (9/22/83 NRC Meeting)
L-83-49 I 9/20/83 (NA)
(B)
RECOVERY PLAN REVISION DRAFT FAILURE MECHANISM ANALYS IS (FMA)
L-83-52 I L-83-53 I I 0/I 3/83 I 0/25/83
Page 3
Office of Nuclear Reactor Regulation Mr. James R. Miller, Chief U. S. Nuclear Regulatory Commission (NA)
(NA)
DRAFT FMA MEETING DRAFT FMA MEETING L-83-545 L-83-558 I I /2/83 I I /I6/83
( I I / I0/83 NRC Meeting)
(NA)
(NA)
(NA)
(NA)
RECOVERY PLAN REVISION REACTOR VESSEL SURVE ILLANCE SPECIMEN-CAPSULE W-97 LP M/IVMDATA ACRS FLUID DYNAMICS SUBCOMMITTEE MEETING L-83-582 L-83-583 I2/I4/83
This submittal has been reviewed and approved by our Company Nuclear Review Board (CNRB) and Facility Review Group (FRG).
Should any questions arise, please contact us immediately.
Very truly yours, J. W. Williams, Jr.
Vice President Nuclear Energy JWW/DAC/cab Attachments cc: HaroldF. Reis
ATTACHMENT I COMBUSTION ENGINEERING, INC.
Statement for Withholding from Public Disclosure Pursuant to IO CFR 9.5(4)
The material. transmitted herewith as Attachment 4 (Draft Copy of the Final Report on the St. Lucie I Post-Cycle 5 Recovery Program), contains information of a nature previously designated as proprietary by Combustion Engineering, Inc., in References I,
2, and 3.
Pursuant to the provisions of IO CFR 9.5(4) of the Commission's regulations, we request that the material be safeguarded.
We believe that withholding this proprietary material will not adversely affect the public interest.
The reasons for the classification of this information as proprietary are:
The use of the information by a competitor would substantially decrease his expenditures, in time or resources, in designing, producing or marketing a similar product.
The information consists of test data or other similar data concerning a
- process, method or component, the application of which results in a
substantial competitive advantage to Combustion Engineering, Inc.
The information reveals special aspects of a process, method, component or the like, the exclusive use of which results in a substantial competitive advantage to Combustion Engineering, Inc.
The information contained in the enclosure is meant to be part of the formal basis for official action by the NRC Staff concerning the St. Lucie Unit I thermal shield removal and core support barrel repair effort.
. References I.
CEN-250(F)-P, "In Service Monitoring of St. Lucie I", May 3I, I 983.
2..
CEN-253(F)-P, "St. Lucie I Core Support Barrel Inspection,.Repair and Analysis, and Thermal Shield Removal", August l6, l983.
3.
CEN-258(F)-P, "St.
Lucie Unit
/7 I Failure Mechanism Analysis Results",
- November, I 983.
Page I of 2 ATTACHMENT2 STATEMENT OF CLARIFICATIONCONCERNING DRAFT FINALREPORT CONTENT Installation experience in the field has necessitated minor design modifications to the expandable plug repair hardware.
Also, patches have been incorporated as part of the core support barrel repair at two lug locations, in addition to that indicated in the enclosed Draft Final Report on the St. Lucie Unit I
Post-Cycle-5 Plant Recovery Program, (i.e., at lug locations 4 and 5).
As a result, information contained in that Report which deals with various aspects of the core support barrel repair (plugs and patches), requires clarification.
It is our intent that the design life objective for plugs and patches be for the remaining life of the plant.
However, difficulty in maintaining tolerances on holes machined underwater in the core support barrel has been experienced at a number of locations.
This has necessitated making compensatory reductions in the expandable plug diameter and/or wall thickness in order to allow plug insertion.
Although these modifications are not extreme, the performance of the plugs may fall outside the tolerance range originally established.
Some of the test and analytical work done previously may have to be repeated for the modified plugs.
Thus, statements made pertaining to the nominal plug design criteria for life expectancy, accommodation of loads and thermal transients resulting from normal operation, and upset and faulted conditions will have to be re-evaluated, possibly on a case by case basis, for the modi fications undertaken.
As earlier stated, the use of patches secured by expandable plugs has become part of the repair at lug locations four and five. A revised summary of plugs and patches is 11 provided in the attached
- table, however, this is not currently reflected in the estimates of bypass leakage discussed in the report or in the plug and patch inventory provided in Table 9.3-I.
The NRC will,.as in the past, be kept abreast of developments and the Final Report, when formally submitted, willcharacterize the nature of the repair at each location and its acceptability compared to the stated design objectives.
Page 2 of 2 PROPRIETARY INFORMATION COMBUSTION ENGINEERING, INC.
ATTACHMENT2 ST. LUCIE UNIT I INVENTORYOF CSB HOLES+
Hole Size (inches) 8D 5D 3D
- 3. I D( I )(4)
Lug No.
I Patch Assembly Lug No. 3 Patch Asembly Lug No. 4 Patch Assembly Lug No. 5 Patch Assembly Lug No. 6 Patch Assembly Number of Holes 8
2 2
I8 30 Total Area inches>
402. I-39.3 I 4. I I 34. I 589.6 87 I (2)(3)(4) 26.3(2)(3) 46.I(2)(3) 55 3(2)(3) 53, I (2)(3)
Total Perimeter (inches) 20 I. I 3 I.4 I 8.8 I 74.2 425.5 (I)
(2)
(3)
(4)
Plugs used to anchor lug patch plates.
Size of patch assembly.
Not a leakage parameter.
Maximum credible size of repair failure (requires simultaneous failure of all four plugs holding in the patch and loss of the patch itself).,
- 87. I in2 29.8 in>
I I6.9 in
+Revision to Table 9.3-I not yet incorporated in report.
ATTACHMENT3 QUALITYASSURANCE The Quality Assurance Programs for FPL and Combustion Engineering are described in this section.
FPL Qualit Assurance Pro ram The FPL Quality Assurance Program is addressed in "FPL Topical Quality Assurance Report" (FPL TQAR l-76A), Revsion 6, June IO, l983.
The Topical Quality Assurance Report is an integral part of Corporate Quality Assurance Manual (FPL-NQA-IOOA).
The control programs described in the following specific NQA-IOOA Quality Procedures have and will continue to be utilized to monitor repair of the core support barrel:
ao QP 4.4, "Review of Procurement Documents for Items and Services Other Than Spare Parts."
Under the provisions of this doc'ument, the FPL Quality Assurance organization reviews and approves all procurement documents issued to Combustion Engineering (C-E) Avery associated with repair of the core support barrel.
b.
QP I8.I, "Conduct of.Quality Assurance Department Quality Audits."
Under the provisons of this
- document, the FPL Quality Assurance organization audits on-site activities to ensure that documented procedures are developed and implemented for such operations as plugging, patching and cleaning of the core support barrel.
Combustion En ineerin Qualit Assurance Pro ram The CE Avery Division Quality Assurance Proagram is described in its Quality Assurance Manual, Rev. I6, April l2, I 983.
Compliance with the requirements of this manual was audited by the FPL Quality Assurance organization in November, l983 with satisfactory results.