ML20236Q059
| ML20236Q059 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 07/13/1998 |
| From: | Peckham M NEBRASKA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20236Q061 | List: |
| References | |
| NLS980104, NUDOCS 9807170294 | |
| Download: ML20236Q059 (6) | |
Text
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1 P.O. BOX B B SKA 68321 Nebraska Public Power District
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NLS980104 July 13,1998 U.S. ' Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555-0001
Subject:
Proposed Change to CNS Technical Specifications, Revision B Conversion to Improved Standard Technical Specifications Cooper Nuclear Station, NRC Docket 50-298, DPR-46
Reference:
1)
Letter from G. R. Horn (Nebraska Public Power District) to U. S. Nuclear Regulatory Commission dated March 27,1997, " Proposed Change to CNS Technical Specifications, Conversion to Improved Standard Technical Specifications" 2)
Letter from J. H. Swailes (Nebraska Public Power District) to U. S.
Nuclear Regulatory Commission dated May 6,1998, " Proposed Change to CNS Technical Specifications, Revision A, Conversion to Improved Standard Technical Specifications" 3)
Letter from J. N. Donohew (U. S. Nuclear Regulatory Commission) to G. R. Horn (Nebraska Public Power District) dated June 24,1998, " Draft Safety Evaluation Regarding Proposed Conversion to Improved Standard Technical Specifications for the Cooper Nuclear Station (TAC No.
M98317)"
Gentlemen:
By letter dated March 27,1997 (Reference 1), Nebraska Public Power District (NPPD) submitted a license amendment request for the conversion of the Cooper Nuclear Station Current Technical
)
Specifications to the Improved Technical Specifications (ITS), as contained in Revision 1 of NUREG-1433, " Standard Technical Specifications General Electric Plants, BWR/4." Following discussion with the Nuclear Regulatory Commission (NRC) and resolution of technical issues, l
Revision A was submitted per Reference 2. The purpose of this letter is to submit Revision B to the proposed ITS license amendment and two proposed license conditions.
The following is a listing of enclosures being provided with this submittal:
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Enclosure A: Summary of Revision B Changes to the ITS Submittal 9807170294 980713 1
PDR ADOCK 05000298 p
PDR E rof f f 9 E M F "
- 9 P M 9 5 "'
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NLS980104 July 13,1998 Page 2 of 4 Enclosure B: Sections affected by Revision B Enclosure C: Proposed License Conditions.
The subject Revision B and proposed license conditions address open issues with the draft Safety Evaluation (Reference 3) that is presently under review. The previously submitted No Significant Hazard Considerations bound these Revision B changes.
l Implementation ofITS is scheduled for August 151998, and is based upon NRC issuance of the Safety Evaluation by July 31,1998 In order to support the ITS issuance schedule, Revision B removes the proposed changes in ITS 3.7.1; " Residual Heat Removal Service Water Booster (RHRSWB) System," 3.7.2; " Service Water (SW) System and Ultimate Heat Sink (UHS)," and 3.7.3; " Reactor Equipment Cooling (REC) System," which credited the fact the sufficient flow exists with one pump per subsystem.
For the same reason, Revision B removes the proposed changes in ITS 3.5.1, " Emergency Core Cooling Systems (ECCS) - Operating," Conditions B and H; these conditions credited the results of an approved SAFER /GESTR LOCA Analysis. As discussed with the NRC, NPPD requests continued review of these proposed allowances, as submitted in References 1 and 2. These changes are highly desirable to avert the potential for unnecessary plant shutdown and transients.
Should you have any questions regarding this revision to the ITS submittal, please contact Mr. Jack Dillich at (402)825-5217.
- Sincerel, M. F.
ham Acting Vice President of Nuclear Energy
-/nr.
Enclosures cc:
Regional Administrator w/ enclosures Associate Director of Projects USNRC - Region IV Senior Project Manager w/ enclosures USNRC - NRR Project Directorate IV-1 1
Senior Resident inspector w/ enclosures J
NLS980104 July 13,1998 Page 3 of 4 Technical Specifications Branch Chief w/ enclosures (6 copies) l USNRC-NRR i
Environmental Health Division - Program Manager w/ enclosures Department of Health State of Nebraska 1
NPG Distribution w/o enclosure l
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NLS980104 i
July 13,1998 l
Page 4 of 4 l
l STATE OF NEBRASKA)
NEMAHA COUNTY) 1 M. F. Peckham, being first duly sworn, deposes and says that he is an authorized representative of the Nebraska Public Power District, a public corporation and political subdivision of the State of Nebraska; that he is duly authorized to submit this request on behalf of Nebraska Public Power j
District; and that the statements contained herein are true to the best of his knowledge and belief.
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I Kf*F. Peckham Acting Vice President of Nuclear Energy l'
pA subscribe in my presence and sworn to before me this 13 day of Jalvt.1998.
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My commission expires: 5-il-A po A
{
Lu4NN BRAY i
by Comm.Eg. May 11,sw Y
NOTARY PUBLIC 4
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l ATTACHMENT 3 LIST OF MRC COMMITMENTS l
l Correspondence No:
NLS980104 i
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l The following table identifies those actions committed to by the District in this l
document. Any other actions discussed in the submittal represent intended or planned actions by the District.
They are described to the NRC for the NRC's l information and are not regulatory commitments.
Please notify the NL&S Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.
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l COMMITTED DATE l
COMMITMENT OR OUTAGE j
None l
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PROCEDURE NUMBER 0.42 l
REVISION NUMBER 6 l
PAGE 9 OF 13 l
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NLS980104 Attachm:nt A l
l Page1 of1 I
SUMMARY
OF REVISION B CHANGES SOURCE DOCUMENT CHANGES DESCRIPTION of CHANGE (S)
Approval of ITS 5.6.5.b Added references (NEDE-23785-1-A and SAFER /GESTR NEDO-31960) to the COLR section of l
LOCA analysis and Chapter 5. These two added references Thermal / Hydraulic relate to the approved analytical methods Stability Solution for used to establish the core operating limits.
j CNS.
i Dran SE ITS 5.7 Retained cmrent licensing basis regarding i
High Radiation Area Controls (CTS 6.3)
Dran SE ITS: 3.5.1 Deleted Conditions B and H to be consistent with NUREG-1433 Bases 3.5.1 l
NRC Request /
ITS 3.7.1 Retained current licensing basis regarding Dran SE ITS 3.7. 2 RHRSWB, SW, and REC.
ITS 3.7.3 Bases 3.7.1 Bases 3.7.2 Bases 3.7.3 NRC request B SR 3.6.1.2.2 Replaced the last sentence with that in NUREG-1433 per NRC request.
NPPD 3.3.5.1-1 ITS Table 3.3.5.1-1 Changed Allowable Value based upon Function 1.d approved calculation using GE Setpoint Methodology.
NPPD 3.3.6.1 ITS Table 3.3.6.1-1 Changed the Allowable Value from "s" to "2" to correct a typographical error.
NRC Comment DOC M.4 Replaced " ASTM-D975-1989a" with ITS 5.5
" ASTM-D1796-1983" as reference to oil centrifuge test.
NRC Comment CTS Markup page 4 of 7 Changed Discussion of Change annotation for ITS 3.3.5.2 for the deletion of Note 2 from "LA.3" to "M.I."
NRC Comment DOC M.1 Revised to state that the restriction on the ITS 4.0 use of the new fuel storage facility is consistent with current plant practice.
NRC Comment DOC M.2 Revised to reflect current practice.
ITS 3.8.3
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