E410-97-040, Submits Addl Info Requested During Audit of TMI USI A-46 Program,970721-25
| ML20203D749 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/02/1997 |
| From: | Noble T GENERAL PUBLIC UTILITIES CORP. |
| To: | Chen P NRC |
| References | |
| REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR E410-97-040, E410-97-40, NUDOCS 9802260133 | |
| Download: ML20203D749 (2) | |
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GPU Nuclear inc.
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Route 441 South NUCLEAR Post Othce Box 480 Middletown, PA 17057 0480 Tel 717 944 7621 (717)948-8669 E410-97-040 September 2,1997 U. S. Nuclear RegWatory Commission Mailstop 07E23 Washington, D.C. 20555 Attn: Mr. Pei-Ying Chen
Subject:
Additional Material-July,1997 TMI USl A-40 Audit
Dear Mr. Pei-Ying Chen:
This transmittal contains additional information requested during your audit of the TMI USl A-46 Program, July 21 through July 25.1997. As we discussed, this material is sent to you directly for your review and i
inclusion in the audit Trip Report. Please feel free to call us if you have any questions.
We offer the following discussion on several issues which were raised during your site visit, as well as several documents (as noted) for your review-1.
As a result of a plant walkdown, the auditors questioned the seismic adequacy of the sight glass and a small bore pipe a3 ached to the Nuclear Services Closed Cooling Water surge tank (NS-T-0001). An evaluation of the consequences of a break and loss of function of the sight glast and pipe was requested as a.) alternate to additional specific seismic evaluation of the appurtenances.
GPUN calculation number C-1101-541-5360-006, NSCCW Loss of Surge Tank inventory, establishes that sufficient NPSH is available if tank inventory is lost. This calculation bounds the consequences of a break and loss of function of both the sight glass and the attached small bore pipe. No further specific evaluation of the appurtenances is required.
2.
The audit team requested, for review, the test data used for establishing design allowables for Uebig expansion anchors.
Attached is a report dated July 30,1980, which contains the results of site tests conducted in April and May of the same year. GPUN Design Guide TMI-0412-1 establishes the allowable design loads which assure a minimum factor of safety of 4.0. An excerpt from the design guide is also attached.
3.
The audit team expressed :;ncern for potential interaction between motor control center 1C-480V-SHES and an electrical conduit which is in close pmximity. The equipment is located in the Fuel Handling Building at elevation 281*. Provide information regarding resolution of this concern.
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.na 9802260133 970902 PDR ADOCK 05000289 P
y.. s GPUN concedes the potential for interaction and has initiated Administrative Work Requeu
- 788927 to re-route the conduit in order to resolve this concern.
4.
The audit team identified corrosion in floor-mounted carbon steel baseplates located in the intake, Screen and Pump House (ISPH). The base plates are for conduit supports, GPUN provided evidence that the condition was identified by the Seismic Review Team and that an outlier was written. An internal memorandum regarding this and other ' housekeeping
- ltems was provided to the auditors. Provide information regarding corrective maintenance for these baseplates.
The corroded conditions cannot be corrected under the Plant Preservation Program which is limited to application of coatings and minor correciive maintenance Therefore an Administrative Work Request, #789103, has been inaiated to provide the repair specifications.
5.
Several documents referenced by GPUN have not yet been reviewed by the NRC. Copies of the following EPRI reports were requested for review and were forwarded under separate cover by EPRl:
IPRI NP-7147-SL Vol. 2 Addendum 1 *Sekmic Ruggedness of Relays
- EPRI NP-7147-SL Vol. 2 Addendum 2 ' Seismic Ruggedness of Relays
- EPRI TR102180 ' Guidelines for Estimation or Verification of Equipment Natural Frequencies
- Copies of the following SQURTS documents, used as references in the GPUN relay calculation (C-1101-900-5320-025), are enclosed:
Test Report Number: 50000.8, Rev.1 Test Report Number: 50090.9, Rev, O Test Report Number: 50093.2, Rev.1 6.
The auditors identified two cable tray supports not selected for the limited analytical review (LAR) which appear relatively heavily loaded. Provide evidence that these supports are not more severely challenged than those selected for the LAR.
Both supports identified have been evaluated per the GIP criteria in a supplemental calculation (EQE calculation number 240031 C-004. Rev 0). In each case 100% cable tray fill was assumed. Also, in each case portions of the support were found to not meet the vertical capacity check. As such they were classified as ou%ers. However, the outliers are resolved within the same calculation by passing the Lateral Capacity Check per GIP criteria. These supports are seismically acceptable and do not represent a challenge more severe than those selected for the LAR.
S:ncerely, Ted Noble GPUN Structural Engineer cc:
S. Ramdeen Y.Nagai EDMS
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