ML17320A653
| ML17320A653 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/04/1983 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR AEP:NRC:0514I, AEP:NRC:514I, NUDOCS 8308080266 | |
| Download: ML17320A653 (16) | |
Text
DOCKET 05000315 05000316 NOTES:
REGULA Y INFORMATION DISTRIBUTI SYSTEM (RIDS)
ACCESSION NBR+8308080266 DOCwDATK: 83/08/04 NOTARIZED; NO FACIL:50 315 Donald C ~
Cook Nuclear Power Plantq Unjt ii 'Indiana 50-316 Donald C,
Cook Nuclear Power Plant~.Unit 2~ Indiana '8 AUTH,NAME AUTHOR AFFILIATION ALEXICH,M~ P Indiana L Michigan Electr ic Co, RECIP ~ NAME RECIPIENT AFFILIATION DENTONeH ~ Re Office of Nuclear Reactor Regulationp Director
SUBJECT:
Responds to NRC 830516 ltr re synopsis of issues associated w/NURKG 0612,Extension.
to 840331 requested due to.necessary modsgper Fr ankl in Reseat ch Ctr draf t technical eval uat ion r ept.,
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USI A-36 Control of Heavy'Load Near Spent Fue1 NUREG-06 RECIPIENT ID CODE/NAME NRR ORB 1 BC INTERNAL; NRR REQUApG 09 AEB REG FILE 04 COPIES LTTR ENCL 7
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INDIANA II MICHIGAN ELECTRIC COMPANY P. O.
BOX 10 BOWLING GR E EN STATION NEW YORK, N. Y. 10004 August 4,1983 AEP:NRC:0514I Donald C. Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 NUREG-0612:CONTROL OF HEAVY LOADS Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
This letter and its Attachment respond to Mr. S. A. Varga's letter of May 16, 1983, which included two enclosures.
Enclosure 1, entitled "Synopsis of Issues Associated with NUREG-0612", contained additional guidance on acceptable solutions to open items.
Enclosure 2, entitled "The Draft Technical Evaluation Report by Franklin Research Center",
identified the open issues in our previous responses submitted to the NRC via our letters No. AEP:NRC:0514C (Phase la), dated June 18,
- 1982, and No. AEP:NRC:0514E (Phase lb), dated September 29, 1982.
In the Draft Technical Evaluation Report (TER), Section 2.1.5.b, Franklin Research Center recommended three options for upgrading the Radiation Protection Shield (RPS) and the Missile Shield (MS) lift
- beams, so that. they would conform to the requirements of Guideline No.4.
We have elected to implement the first option, i.e. modification to the existing beams and/or redesigning new beams.
The engineering/design of the liftbeams was started after the receipt of the TER. As such we will require an extension to the implementation date required by NUREG-0612 from September 22, 1983 to March 31, 1984.
In the interim period the present lift beams can be safely operated since they have been designed as per the AISC Guidelines using a factor of safety of 1.5 and 2.0 for yield stress and have been load tested at 110% of the load.
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"Crane Operator Training" was approved and issued in September 1982.
The MHI will be revised to comply with the requirements of Guideline 3.
TER SECTION 2.1.5.c CONCLUSION AND RECOMMENDATIONS "Special lifting devices at D. C. Cook Units 1 and 2 do not comply with Guideline 4.
To demonstrate compliance, the Licensee should perform the following:
For the reactor vessel head and internals lift rig, complete the overall assessment which should include verification of design adequacy of the devices as well as the implementation of a program to ensure continuing compliance in accordance with ANSI N14.6-1978, Section 5.
For the RPS and MS lifting devices, implement one of the above listed options or propose a suitable alternative".
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C Technical Evaluation Report AEP:NRC:0514I
RESPONSE
TO SECTION 2.1.5.c The reactor vessel head and internals liftrig response was submitted in our letter No.AEP:NRC:0514G, dated July 5, 1983.
Attachment No.l to the above letter is the Westinghouse WCAP No.
10230 and contains a comparison of ANSI N 14.6-1978 requirements and Westinghouse requirements.
Attachment No.2 to the above letter contains the Indiana 6 Michigan Electric Company's responses to the Westighouse recommendations.
The Radiation Protection Shield (RPS) and the Missile Shi.eld (MS) liftbeams have factors of safety of 1.5 and 2.0, respectively, as reported previously.
These are limiting safety factors determined for the existing lifting beam assemblies.
In order to establish design margins consistent with the ANSI N14.6-1978 values of 3 for minimum yield and 5 for ultimate
- strength, new liftbeam assemblies have been designed for both RPS and MS 'lift beams which meet these requirements.
The MS liftbeam assembly has been sent to purchasing for the selection of and the release to a fabricator.
A design has also been made to allow reinforcing the existing RPS lift beam assembly.
The reinforced, assembly would meet the ANSI sa fety factor requirements.
The RPS lift beam assembly is undergoing an evaluation to determine whether a
new lift beam assembly should be acquired or whether the existing lift beam assembly should be reinforced. It's anticipated that the new and/or modified RPS and MS lift beams will be ready for use by March 1984.
TER SECTION 2.1.6.c CONCLUSION r
"The D. C. Cook Plant complies with Guideline 5 of NUREG-0612".
RESPONSE
TO SECTION 2.1.6.c No response is required.
TER SECTION 2.1.7.c CONCLUSION AND RECOMMENDATIONS "D.
C.
Cook Units 1
and 2 partially comply with Guideline 6 of NVREG-0612.
In order to comply fully, the crane maintenance program and procedures should be revised to include criteria of ANSI B30.2-1976 related to component, repair and replacement and wire rope maintenance".
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Technical Evaluation Report AEP:NRC:0514Z
RESPONSE
TO SECTION 2.1.7.c The area of crane repair and maintenance is a rather broad area and it is difficult to predict all items that may eventually require repair and maintenance.
Therefoxe, we believe it
~ is prudent to restrict the subject of repair to those items described in Paragraph 2-2.3.3-C of ANSI B30.2-1976.
Similarly, the subject of maintenance will concern the items identified by Whiting Corporation in their operation and maintenance manuals as those which require periodic maintenance.
Maintenance procedures will be upgraded to include the above requirements.
I The maintenance outlined in Paragraphs 2-2. 3. 1 and 2-2. 3. 2 of ANSI B30.2-1976 will be incorporated into the maintenance procedures.
The Rope Inspection, Replacement, and Maintenance outlined in ANSI B30.2-1976, Section 2-2.4, will be incorporated into the maintenance procedures.
TER SECTION 2.1.8.c CONCLUSION AND RECOMMENDATIONS "The polar cranes at D.
C.
Cook Units 1
and 2
comply with Guideline 7 of NUREG-0612.
Contingent upon completion of modifications proposed for both the auxiliary building crane and the CW pump and screen house
- crane, these cranes will comply with this guideline.
- However, the auxiliary building crane should be restricted to a
capacity of 75 tons until resolution of the drum pinion strength and gear durability questions and subsequent review 'by the NRC".
RESPONSE
TO SECTION 2.1.8.c The modifications to the auxiliary building crane consisting'f (1) installation of additibnal longitudinal stiffeners to the crane
- girders, and (2)
- welding of bars to the end truck plates across the runway rail head near each bridge wheel have been completed.
In addition, the capacity of the auxiliary building crane is restricted to 75 tons until the drum pinion and drum gear are replaced.
Upon replacement of these components,"
a load test will be performed and after satisfactory completion of this test, the capacity of the auxiliary building crane will be restored to 150 tons.
The replacement of the pinion and gear will not take place until 1984 because of long lead times for these components.
TER SECTION 2.2.l.b CONCLUSION "D. C.
Cook Units 1 and 2 comply with Interim Protection Measure
RESPONSE
TO SECTION 2.2.l.b No response is required.
1 f
Technical Evaluation Report
~ AEP: NRC: 0514Z TER SECTION 2 ' '
b EVALUATIONS@ CONCLUSIONS'ND RECOMMENDATIONS "Evaluations, conclusions, and recommendations are contained in discussions of the respective general. guidelines in Sections 2.1.2, 2.1.3, 2.1.4, and 2.1.7".
RESPONSE
TO SECTION 2.2.2.b No response is required.
TER SECTION 2 ~2.3.b CONCLUSION AND RECOMMENDATZON "The D.
C.
Cook Plant substantially complies with Interim Protection Measure 6.
In order to fully comply, the Licensee should perform a
visual inspection of load bearing components of special lifting devices used to handle heavy loads over the
- core, pending completion of the full design and continuing compliance review being performed in accordance with Guideline 4".
RESPONSE
TO'SECTION 2'.3.b This item was included in our letter No, AEP:NRC:0514G dated July 5, 1983.
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