ML20011E153

Provides Currently Identified Outage & nonoutage-related Activities to Update NRC of Util Licensing Activities in Order of Priority

ML20011E153
Person / Time
Site:	River Bend
Issue date:	01/29/1990
From:	Booker J GULF STATES UTILITIES CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RBG-32215, NUDOCS 9002080211
Download: ML20011E153 (6)

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GULF STATES UTELITIES COMPANY fliviE ti[ND 51 Af sDN PM1 O6 H(l DDX 270 $1 16tA%gGyut (Duit, LANA 7(>776 AMA0004bN $35 t@4 346 66bt January 29,1989 RBG-32215 File Nos. G9.5, G9.42 U. S._ Nuclear Regulatery Commission Document Control. Desk Washington, D.C. 20555 Gentlemen:

River Bend Station - Unit 1 Docket No. 50-458 This letter is provided to update the NRC Staff River Bend

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Station (RBS) Project Manager on Gulf States Utilities Company's (GSV) Licensing activities in support of RBS. The enclosed attachment provides the currently identified outage and non-outage related activities in order cf their respective GSU priority. Should activities or priorities change or require special attention, GSU will promptly notify you.

Your support of previously completed activities and these upcoming activities is appreciated. If additional information is required, please contact Mr. L. A. England Director-Nuclear Licensing at (504) 381-4145.

Sincerely, V ?.Le*&/52) n~ 9.

J E. Booker Manager-River Bend Oversight JEB/L4 L BMB/ch Attachment g0\

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cc: U. S. Nuclear Regulatory Commission r Region IV ,

611 Ryan Plaza Drive, Suite 1000 '

Arlington, TX 76011  :

NRC Resident Inspector Post Office Box 1051 l i St. Francisville LA 70775 '

Mr. Walt A. Paulson RBS Project Manager ,

i- Document-Control Desk i Washington, D.C. 20555 i

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LICENSE NElWENT REQUEST ,

PRIORITY M S STATUS GSU 585tITTAL PRIORITY DESCRIPTION / STATUS TO IWIC EXPECTED SER Refueling Outage 3 Amendments 1 Generic Letter 89-14 deletes requirements for 3.25 limit on sent 2/90 surveillance intervals of Specification 4.0.2.

2 Incorporate Generic Letter 87-09 into license to allow mode changes sent while relying on certain Action statements and provide additional surveillance requirement guidance.

Response to NRC RAI for GSU to provide specific justification for 2/90 8/90 each Specification 3.0.4 change which must address how an ' equivalent level of safety is maintained' has been issued for internal review.

NRC SER for 4.0 Specifications expected separate from the 3.0 Specification changes.

3 Reload cycle specific parameter Technical Specification change to sent 3/90 reference core operating limits report (Generic Letter 88-16).

4 Amendment request to revise Technical Specification 3/4.9.6 to allow 3/90 8/90 control rod removal and transfer with refueling and fuel handling platforms.

5 Transfer of snubber requirements from Technical Specifications sent 2/90 to the approved ASME inservice inspection plan (ISI).

Justification demonstrates that the ASME-ISI plan and Technical Specification 4.0.5 provides sufficient control of snubber requirements.

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D g, h ssu stentTTat PRIORITY DESCRIPTION / STATUS TO IRC EXPECTED Sat -

6 Amendment recuest to include final design modification (MR 86-0971) TBD TBD to provide chilled water to drywell unit coolers. The final design is under development by Engineering.

7 Request to delay License Condition 2(c)8 Attachment 3, item 2 from 2/90 8/90 from RF3 until RF4 to coinside with the five year diesel crank shaft inspection plan.

8 Revise current diesel generator surveillarece requirement to perfom 2/90 8/90 LOP test within 5 minutes of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> run to performance within 5 minutes after a one hour run. Justiffcation will demonstrate that-this change has no effect on reliability and will allow more flexible test scheduling.

9 Investigate shutdown ECCS requirements to allow one loop of 3/90 9/90 RHR in shutdown cooling with manual alignment for vessel injection (EEAR 89-231). Justification under development by Engineering.

10 Develop reload submittal for Cycle 4. Will be necessary if TBD 9/90 submittal per GL 88-16 is delayed.

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GSU SIMIITTAl.

PRIORITY DESCRIPTION / STATUS TO INic EXPECTED SER. *

~flon-Refueling Amendments 1 Deletes Technical Specification requirements of annulus radiation 4/90 TBD monitors 11A and 118. Justification will demonstrate that the monitors are not required to cperate to support the safety analysis.

2 Revises surveillance requirement to allow continued plant operation 2/90 TBD for more than 31 days when reactor water conductivity is being monitored by manual sampling in lieu of installed instrumentation.

Justifica S on demonstrates operation for more than 31 days with manual sampling will maintain adequate monitoring of reactor water chemistry.

3 Increases the reactor protection system allowable outage times from TBD TBD 2 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and surveillance frequency from 31 days to 92.

Justification based on BWROG report which demonstrates no significant change to reliability.

4 Revised requirements to start and load operable diesel generators sent review when offsite sources are inoperable and changes conditions requiring under BWROG plant shutdown when redundant equipment is out of service. submittal Justification demonstrates increased reliability by reducing unnecessary starts of operable diesel generators.

GSU was the lead plant for this BWROG Technical Specification improvement item. The NRC has decided to review this concept under the improved Technical Specification program.

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GSU SIMIITTAL -

PRIORITY DESCRIPTION / STATUS 70 NRC EXPECTED SER '

5 Revises Specification 4.0.5 per GL 88-01. Request is on hold pending TBD TBD NRC decision to include this item in the Improved Technical Specifications.

6 Request to extend DG start times' from 10 seconds to 30 seconds TBD TBD 7 Request to ansnend reactor pressure / temperature curves per RG 1.99, 2/90 8/90 Rev. 2 (GL 88-11)

Recent Amendments Received n/a Request a delay of RG-1.97 neutron monitoring until resolution of sent- received BWROG-NRC discussions involving the GE Topical. Report. Amendment 39 n/a Includes additional drywell electrical outlets to penetration sent received overcurrent protection. specification. Justification demonstrates Amendment 40 that the design of the additional outlets is identical to those presently in place.

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