W3P85-2179, Application for Amend to License NPF-38,consisting of Tech Spec Change Requests NPF-38-04,05,06 & 07,revising First Inservice Visual Insp Period for Inaccessible Snubbers & Correcting Steam Generator Temp Limitation.Fee Paid
| ML20132H046 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 08/01/1985 |
| From: | Cain J LOUISIANA POWER & LIGHT CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20132H049 | List: |
| References | |
| W3P85-2179, NUDOCS 8508050232 | |
| Download: ML20132H046 (8) | |
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70160 9 1504J 5G5-2204 MIDDLE GOUTH UTIUTIES SYSTW August 1, 1985 JM. CAIN President and Chief Executive Officer W3P85-2179 3-A1.01.04 A4.05 Director of Nuclear Reactor Regulation Attention:
Mr. G.W. Knighton, Chief Licensing Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
SUBJECT:
Waterford SES Unit 3 Docket No. 50-382 Technical Specification Change Requests NPF-38-04, NPF-38-05, NPF-38-06, NPF-38-07
Dear Sir:
Louisiana Power & Light hereby files an application for four amendments to the Waterford 3 Technical Specifications. The amendments involve:
1.
A correction of three typographical errors in component designations, 2.
A revision to the first insei vice visual inspection period for inaccessible snubbers, 3.
A clarification to indicate that the spent fuel handling machine is not required for movement of new fuel assemblics outside the spent fuel pool, and 4.
A correction to the steam generator temperature limitation to reduce the potential for brittle failure in the event of an overpressure condition.
The enclosed proposed c.hanges do not involve an unreviewed safety question nor a significant hazards consideration.
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-Page 2 Should~ you have any questions or require additional information concerning these requested changes, please contact Mike Meisner at (504) 595-2832.
Yours very truly, r
.M. Cain President and Chief Executive Officer
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Enclosures:
NPF-38-04 NPF-38-05 NPF-38-06 NPF-38-07 t
cc:
B.W. Churchill, W.M. Stevenson, R.D. Martin, D.M. Crutchfield, J. Wilson, T.A. Flippo, Administrator Nuclear Energy Division (State of Louisiana) i
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UNITED STATES OF AMERICA NUCLEAR REGULATORY. COMMISSION In the matter of
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Docket No. 50-382 L'
Louisiana Power & Light Company Waterford 3 Steam Electric Station
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l AFFIDAVIT J.M. Cain, being duly sworn, hereby deposes and says that he is President and Chief Executive Officer of Louisiana Power & Light Company; that he is duly authorized to sign and file with the Nuclear Regulatory Commission the attached Technical Specification Change Requests; that he is familiar with the content thereof; and that the matters set forth therein are true and l
correct to the best of his knowledge, information and belief, i
J.MfC'ain President and Chief Executive Officer STATE OF LOUISIANA)) ss PARISH OF ORLEANS )
Subscribed and sworn to before me, a Notary Public in andj^or the' Parish.
and State above named this
/sI day of M, u)_,
, 1985.
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h Notary Public V'l d[ /.%
- ng4, My Commission expires
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' DESCRIPTION AND-SAFETY ANALYSIS OF PROPOSED CHANGE NPF-38-04 insis is. a request to revise Table 3.8-1, '" Containment Penetration Conductor Overcurrent Protective Devices" of Technical Specification 3/4.8.4,
" Electrical Equipment Protective Devices" by correcting three typographical
. errors in the: Table. This request is submitted for Waterford SES Unit 3.
Existing Specifications See Attachment A Proposed Specifications See Attachment B Description Technical. Specification 3/4.8.4 delineates the operability and surveillance requirements for the containment penetration conductor overcurrent protective devices listed in Table 3.8-1.
The requirements of this Technical Specifica -
i=
. tion ensure these devices will not prevent safety related valves from
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performing their function. The proposed change to Table'3.8-1 consists of the following 3 parts:
(a)
Item 8, 480 Volts Power from MCCs, Table 3.8-1, page 3/4 8-24 currently lists the valve number as 1SI-V1508 TK IB.
The proposed change will correct the typographical error in the tank designation suffix to accurately list the valve number as ISI-V1508 TK 2B.
(b)
Item #57, 120 Volts Control Power from PDPs or MCCs, Table 3.8-1, page 3/4 8-39 currently lists the Power Distribution and Motor Data (PDMD)' sheet number for primary protection as 148. The proposed change will correct the typographical error to accurately list the.
PDMD sheet number as 148A.
-(c)
Item 71, 120 Volts control Power from PDPs or MCCs, Table 3.8-1 page 3/4 8-41 currently lists the valve number as 2BM-P237. The proposed change will correct the typographical error in the code class prefix to accurately list the valve number as 7BM-P237.
Safety Analysis
'The proposed change described above shall be deemed to involve a significant hazards consideration if there' is a positive finding in any of the following areas:
1.
Will operation of the facility in accordance with this proposed change involve a significant increase in the J
probability or consequences of any accident previously j
evaluated?
1 i
i
o t Response: No The proposed change will correct the typographical errors in Table 3.8-1 resulting in agreement between the Technical Specifications and other plant documents.
Therefore, the proposed change will not involve an increase in the probability or consequences of any accident previously evaluated.
2.
Will operation of the facility in accordance with this proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No Correcting the typographical errors in Table 3.8-1 introduces no new perturbation to the plant hardware or procedures. Therefore, the proposed change will not create the possibility of a new or different kind of accident from any accident previously evaluated.
3.
Will operation of the facility in accordance with this proposed change involve a significant reduction in a margin of safety?
Response: No Correcting the typographical errors in Table 3.8-1 introduces no new perturbation to the plant hardware or procedures. Therefore, the proposed changes will not involve a reduction in the margin of safety.
The Commission has provided guidance concerning the application of standards for determining whether a significant hazards consideration exists by providing certain examples (48 FR 14870) of amendments that are considered not likely to involve significant hazards considerations. Example (i) relates to a purely administrative change to technical specifications, (i.e.
a change to achieve consistency throughout the technical specifications, correction of an error, or a change in nomenclature).
The proposed changes to Table 3.8-1 as described in parts a, b, and c above, will correct the typographical errors and bring the Technical Specification into conformance with other plant documents. Therefore, the proposed change is similar to example (1).
Safety and Significant Hazards Determination Based on the above Safety Analysis, it is concluded that:
(1) the proposed change does not constitute a significant hazards consideration as defined by 10 CFR 50.92; and (2) there is a reasonable assurance that the health and safety of the public will not be endangered by the proposed change; and
(3) this action will not result in a condition which significantly alters the impact of the station on the environment as described in the NRC Final Environmental Statement.
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r-e NPF-38-04 ATTACHMENT A