ML17347A732

Forwards Revised Tech Specs Re Administrative Controls for 880219 Application for Amends to Licenses DPR-31 & DPR-41, Per NRC Request.Understands That Discretionary Enforcement Granted by NRC 880115 Ltr Will Remain in Effect

ML17347A732
Person / Time
Site:	Turkey Point
Issue date:	04/22/1988
From:	Conway W FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML17347A733	List: ML17347A732 ML17347A734
References
GL-88-06, GL-88-6, L-88-189, NUDOCS 8805030223
Download: ML17347A732 (7)

Text

I'g AC CEIZMTED DI IBUTION DEMONSTR i'ION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8805030223 DOC.DATE: 88/04/22 NOTARIZED: NO DOCKET FAClL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C 05000250 50-251 Turkey Point Plant, Unit 4, Florida Power and Light C 05000251 AUTH. NAME AUTHOR AFFILIATION CONWAY,W.F. Florida Power 6 Light. Co.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards revised Tech Sections 6.5.1.6.e,6.5.1.7.c, 6.5.1.8 6 6.6.1.b,per NRC request. I DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE-TITLE: OR Submittal: General Distribution NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 0 PD2-2 PD 5 5 EDISON,G 1 1 INTERNAL: ARM/DAF/LFMB 1 0 NRR/DEST/ADS 7E 1 1 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/MTB 9H NRR/DOEA/TSB OGC 15-B-18 ll 1 1

1 1

1 0

NRR/DE ST/RS B 8E RR%PMAS/ILRB12 EG FI~L Ol 1

1 1

1 1

1 RES/DE/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 A

TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 18

II April 22, 1988 L-88-189 U.,S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:

Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Proposed License Amendment Administrative Controls By letter dated Pebruary 19, 1988, Plorida Power k Light Company (PPL) requested that Appendix A of Facility Operating License DPR-31 and DPR-41, Turkey Point Units 3 and 4 Technical Specifications, be amended to revise Section 6, Administrative Controls, by deleting Pigures 6.2-1 and 6.2-2, the off-site management and plant organization charts, and replacing them with general organization requirements which reflect the significant organizational features depicted in the charts for ensuring that the plant will be operated safely. Other changes were also made to reflect recent and proposed organization changes affecting the onsite and offsite organizations, to revise the designation of the Chairman of the Company Nuclear Review Board, to revise reporting requirements with respect to the Plant Nuclear Safety Committee, and to delete the requirement that the Operations Superintendent hold a Senior Reactor Operator (SRO) License.

At the request of the NRC Staff, PPL has revised Technical Specification Sections 6.5.1.6.e, 6.5.1.7.c, 6.5.1.8, 6.6.l.b, 6.7.l.b, and 6.7.l.d by replacing "Senior Corporate Nuclear Officer" with "Senior Vice President-Nuclear." Technical Specifications 6.2.1.b and 6.2.l.c were also revised to identify the positions having the stated responsibilities.

These changes are editorial, and are consistent with the guidance included in Generic Letter 88-06, Removal of Organization Charts from Technical Specification Administration Control Requirements, issued by the NRC on March 22, 1988. We request that you defer action on the proposed change deleting the Operations Superintendent SRO License requirement until the NRC Staff has decided on a position. Accordingly, TS 6.2.2.h has been added reflecting the current TS requirement.

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8805030223 880422 PDR ADOCK 05000250 I/(

P DCD an FpL Group company

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U. S.. Nuclear Regulatory Commission

'L-88-189 Page two It is our understanding that the discretionary enforcement granted by the NRC letter dated January 15 1988, regarding the incumbent Operations Superintendent, will remain in effect until the issue is resolved by a subsequent amendment request.

Revised pages reflecting these changes are attached. The basis for the no significant hazardous determination provided with our Pebruary 19, 1988 request is not affected by these changes.

If there should be any questions regarding this subject, please contact us.

Very truly yours, W. P. Conway Acting Group Vice President Nuclear Energy WPC/TCG: md Attachment Cco Dr. J. Nelson Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant Mr. Jacob Daniel Nash, Plorida Department of Health and Rehabilitative Services

ATTACHMENTTO LICENSE AMENDMENT AMENDMENT NO. FACILITYOPERATING LICENSE NO. DPR-31 AMENDMENTNO. FACILITYOPERATING LICENSE NO. DPR-41 Revise Appendix A as follows:

Remove Pa es Insert Pa es Vl Vl 6-1 6-1 6-la Figure 6.2-1 6-2 Figure 6.2.-2 6-3 Table 6.2-1 6-5 6-5 6-V 6-8 6-9

LIST OF FIGURES

~FI ure Title

2. 1-1 Reactor Core Thermal and Hydraulic Safety Limits, Three Loop Operation 2.1-la Deleted

2. 1-lb Deleted 2.1-2 Reactor Core Thermal and Hydraulic Safety Limits, Two Loop Operation

3. 1-1 DOSE EQUIVALENT 1-131 Primary Coolant Specific Activity Limit Versus Percent of RATED POWER with the Primary Coolant Specific Activity > 1.0 pCi/gram Dose Equivalent 1-131 3.1-1a Reactor Coolant System Heatup and Cooldown Pressure Limits 3.1-1b Reactor Coolant System Heatup and Cooldown Pressure Limits 3.1-1c Reactor Coolant System Heatup and Cooldown Pressure Limits 3.1-1d Reactor Coolant System Heatup and Cooldown Pressure Limits 3.1-2 Radiation Induced Increase in Transition Temperature for A302-B Steel

3. 1-2c Radiation Induced Increase in Transition Temperature for A302-B Steel 3.1-2d Radiation Induced Increase in Transition Temperature for A302-B Steel 3.2-1 Control Group Insertion Limits for Unit 4, Three Loop Operation 3.2-1a Control Group Insertion Limits for Unit 4, Two Loop Operation 3.2-1b Control Group Insertion Limits for Unit 3, Three Loop Operation 3.2-1c Control Group Insertion Limits for Unit 3, Two Loop Operation 302 2 Required Shutdown Margin 3~2 3 K (z) vs Core Height 3.2-3a Deleted 3.2-4 Maximum Allowable Local KW/FT 4.12-1 Sampling Locations 5.1-1 FPL Turkey Point Site Area Map 6.2-1 Deleted 6.2-2 Deleted B3.1-1 Effect of Fluence and Copper Content on Shift of RTNDT for Reactor Vessel Steels Exposed to 550 F Temperature B3.1-2 Fast Neutron Fluence (E > 1MEV) as a function of Effective Full Power Years B3.2-1 Target Band on Indicated Flux Difference as a Function of Operating Power Level B3.2-2 Permissible Operating Band on Indicated Flux Difference as a Function of Burnup (Typical)

'v1- Amendment Nos. and