RBG-41056, Provides Clarifications to LAR 91-11 Re Removal of Component Lists
| ML20078H073 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 11/10/1994 |
| From: | James Fisicaro ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20078H077 | List: |
| References | |
| RBF1-94-0099, RBF1-94-99, RBG-41056, NUDOCS 9411170007 | |
| Download: ML20078H073 (4) | |
Text
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Entsrgy Opsretiona. Inc.
Ryer Bend S:aton c485 US H:ghway 61 Po Box 220
~=~ENTERGY st r< enc'sv'ite 'A 707r5
+
(504) 336-6225 rAX (504) t45-5000 JAMES J. FISICARO Director Nuclear Sa'ety i
November 10,1994 t
U. S. Nuclear Regulatory Commission Document Control Desk Mail Stop PI-37 Washington, DC 20555
Subject:
River Bend Station - Uni' 1 Docket No. 50-458 License No. NPF-47 License Amendment Request (LAR) 91-11, Removal of Component Lists File Nos.:
G9.5, G9.42
Reference:
- 1) RBG-39894, dated January 14,1994 RBFb 94-0099 RIiG-41056 Gentlemen:
On January 14, 1994, Entergy Operations Inc. (EOI), submitted an application for amendment to the River Bend Station (RBS) Technical Specifications (Reference 1). Included were proposed changes which would remove component lists from the Technical SpeciDeations per guidance provided in NRC Generic Letters 91-01 and 91-08.
Recently, NRC Staff and RBS personnel discussed several clarifications to the information provided in Attachment 1 of RBG-39894. Attachment I to this letter contains these r
clarifications. RBS recommends including these clari0 cations into the previously submitted license amendment request. Attachment 2 contains the originally submitted Technical I
Specification pages marked up to reflect the clari0 cations. The proposed clari0 cations are editorial and do not impact the scope of the original submittal; therefore, they are bounded by the No Significant Hazards Considerations previously submitted in RBG-39894.
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9411170007 941110 0g PDR ADOCK 05000458 p
PDR 1
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Liwase Amendment Request 91-11 P.BC 1-94-0099 RBG-41056 November 10,1994 Page 2 of 2 If you have any questions or conunents, please contact Mr. Otto P. Bulich of my staff at (504) 336-6251.
Very truly yours, A
.jb4%
GHD/jr attachments cc: Mr. David L. Wigginton U. S. Nuclear Regulatory Commission M/S OWFN 13-H-2 Washington, DC 20555 NRC Resident Inspector P. O. Box 1051 St. Francisville, LA 70775 U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 7601
License Amendment Request 91-11 RBF1-94-0099 RBG-4105fr Page 1 of 2 PROPOSED CLARIFICATIONS TO LAR 91-11 Listed below are proposed clarifications to LAR 91-11 based on discussions with the NRC.
These clarifying changes are editorial and are bounded by the No Significant Hazards Considerations previously submitted in RBG-39894. Changes to the original submittal are denoted in hold italics.
- 1. Attachment 1, Page 20,Section XII, PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES (3/4.8.4.1) a.
Revise LCO 3.8.4.1 to read as follows:
"Each of the primary and backup (' containment penetration conductor' deleted) overcurrent protective devices associated with each primary containment electrical penetration circuit shall be OPERABLE. The scope of these protective devices excludes those circuits for which credible fault currerits would not exceed the electrical penetrations' design ratings."
- b. Revise ACTION Statement 3.8.4.1 to read as follows:
"With one or more of the (' primary containment penetrution conductor' deleted) overcurrent protective devices inoperable, declare the affected system or component inoperable and apply the appropriate ACTION s.atement for the affected system and:
- c. Revise Surveillance Requirement 4.8.4.1 to read as follows:
"Each of the (' primary containment penetration condnctor' deleted) overcurrent protective devices shall be demonstrated OPERABLE:
- 2. Attachment 1, Page 22,Section XIII, OTHER OVERCURRENT PROTECTIVE DEVICES (3/4.8.4.2) a.
Revise LCO 3.8.4.2 to read as follows:
"Each primary (' required' deleted) overcurrent protection devicefor the Main Control Room safety-related lighting and the primary and secondary RPS Alterriate Source of Power shall be OPERABLE."
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License Amendment Request 91-11 RBF1-94-0099 RBG-41056 Attachment i Page 2 of 2
- 3. Attachment 1, Page 23,Section XIV, A. C. CIRCUITS INSIDE CONTAINMENT (3/4.8.4.4) a.
Revise LCO 3.8.4.4 to read as follows:
"Each 480 V and 240/120 V (' required' deleted) A. C. circuit inside containmentfor the Containment Building IIVAC, Drywell Cooling HVAC, RWCU, Inclined Fuel Transfer Tube, and Reactor fluilding Main Iloist systerns without redundant penetration protection shali be de-energized."
- b. Revise ACTION Statement 3.8.4.4 to read as follows:
"With any ('of the required' deleted) A. C. circuit energized, trip the associated circuit breaker (s) in the specified location within I hour."
- c. Revise Surveillance Requirement 4.8.4.4 to read as follows:
"Each ('of the required' deleted) A. C. circuit shall be detennined to be de-energized by verifying at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ** that the associated circuit breakers are in the tripped condition."
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