ML17354A838

Proposed Tech Specs Deleting License Conditions 3.I,3.K,3.H & 4 & Incorporating Recent Organization Change in TS 6.5.1.2 & 6.5.3.1.a

ML17354A838
Person / Time
Site:	Turkey Point
Issue date:	03/12/1998
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17354A833	List: ML17354A832 ML17354A838
References
NUDOCS 9803180098
Download: ML17354A838 (18)

Text

L-98-Z6'Attachment 3 ATTACHMENT 3 PROPOSED LICENSE AMENDMENTS FOR ADMINISTRATIVE CHANGES TO FACILITY OPERATING LICENSES AND TECHNICAL SPECIFICATIONS PROPOSED FACILITY OPERATING LICENSE PAGES DPR-31 pages 4 through 8 PROPOSED FACILITY OPERATING LICENSE PAGES DPR-41 pages 5 through 9 PROPOSED TECHNZCAL SPECIFICATIONS PAGES FIGURE 5.1-2 Section 6 page 6-6 Section 6 page 6-11 9803180098 980312 PDR ADOCK 05000250 P PDR DPR-31 Page 4 H.DELETED o~4%The Turkey Point Plant steam generator repair program, as described in the licensee'"Steam Generator Repair.Report" dated September 20, 1977, as supplemented on December 20, 1977, March 7, April 25, June,20 and August 4, 1978, January 26, 1979 and March 28, 1980, and the affidavit of A.J.Gould dated June 12, 1981, for Unit No.3 is approved pursuant to the Atomic Safety and Licensing Board Final Order dated June 19, 1981.(2)uring the repair program the following temporary li ense conditions*

will be imposed: (a)All el shall be removed from the reactor pressure vessel f the unit under repair and stored in the spent fuel poo (b)The health hysics program and procedures which have been establis ed for the steam generator repair program shall be impl ented.(c)Progress reports all be provided at 60-day intervals from the start of he repair program and due 30 days after close of th interval with a final report provided within 60 day after completion of the repair.These reports will incl e: A summary of the occ ation exposure expended to date using the format and detail of Table 3.3-2 of the"Steam Gener or Repair Report" as supplemented.

An evaluation of the ef ctiveness of dose reduction techniques as spe ified in Section 3.3.5 of the"Steam Generator pair Report" as supplemented in reducing occupati nal exposures.(iii)An estimate of radioactivity relea ed in both liquid and gaseous effluents.(iv)An estimate of the solid radioactiv waste generated during the repair effort inc uding volume and radioactive content.*Reference in parentheses refer to the Safety Evaluation Report (NUREG-0756)December, 1980.

DPR-31 Page 5 (d)Procedures shall be prepared to assure that power can be restored by manual operator actions to the fuel pool of the unit undergoing repair within.eight hours (3.2.2.2).(e)The remedy chosen by FPL to provide the availability of the diesel fuel supply while the oil-retention dike is removed from the main diesel saf ety tank shall'be addressed and adequately demonstrated by FPL prior to initiating the construction changes affecting the dike (3.2.2.2).

'xty days prior to fuel loading, the program for p operational testing and startup shall be submitted fo NRC review (2.7).(g)Sixty ays prior to fuel loading, FPL should submit for evaluat'on by the NRC a steam generator secondary water chemist control and monitoring program (3.2.4)which will addr s the following:

Ident fication of a sampling schedule for the critic parameters and of control points for these p rameters for each mode of operation:

normal op ation, hot startup, cold startup, hot shutdown, old wet layup;(ii)Identificatio of the procedures used to measure the values of e critical parameters;(iii)Identification o process sampling points;(iv)Procedure for the ecording and management of data;(v)(vi)Procedures defining corr ctive actions*for off-control point chemistry nditions;and A procedure identifying (a)the authority responsible for the in'terpr ation of the data and (b)the sequence nd timing of administrative events requir to initiate corrective action.Branch Technical Position KZEB 5-3 describes the cceptable means for monitoring secondary side water chemistr in PWR steam generators, including corrective actions f off-control point chemistry conditions.

However, the st ff is amenable to alternatives, particularly to Branch Tec'al Position B.3.b(9)of HTEB 5-3 (96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> time limit to re ir or plug confirmed condenser tube leaks).

DPR-31 Pa FPL should verify that the steam generator secondary water chemistry control program incorporates technical recommendations of the NSSS vendor.Any significant deviations from NSSS vendor recommendations should be noted and justified technically.(h)Sixty days prior to the decontamination of the channel head, FPL should meet the following conditions

'(3.2.5): A system should be set up so that the pressure in the inflatable plug seal in the RCS pipe nozzles should be monitored.

Upon loss of seal pressure, injection of the grit slurry should be topped immediately and the seal plug replaced.(ii)Wr'tten procedures should be provided to include acc untability controls of all tools, equipment, mate ials, and supplies that are to be used in the c annel heads to prevent inadvertent entry of suc items into the reactor primary coolant system.These controls should be in effect whenever he inflatable plug seals and their associated over plates are not in place in the nozzles of e reactor coolant system piping.(iii)Written proc ures should be provided to restrict mater's to be used in the channel head area to pre ent the presence of materials having potential verse effects on the reactor coolant system omponents (f or example, chloride-bearing mat ials).(iv)Written procedures shou be provided to include instructions to require that the channel head area, including the nozz es, be inspected and confirmed to be free of ll loose materials, equipment, and tools prior t removing the cover plate from the inflatable plu seal.(v)P ior to closing up the reacto coolant system and starting the RCS pumps, any loose debris, including the abrasive grits, i the channel head, ,RCS hot leg, and cold le should be cleaned up.(vi)Prior to resumption of power operat'on, the licensee should submit for NRC revx w and acceptance a report which will inclu e an analysis of the possible effects of any fo eign material which has entered the primary coo nt system and has not been retrieved.

The rep t should include all work on the decontaminatio and steam generator repair.

DPR-31 Page 7 Sixty days prior to the movement of the used steam generator lower assemblies from the containment, the rocedures for the move, associated QA requirements, an description of the equipment to be used shall be provide the NRC (3.2.6.).(j)Before storage or'ent of the used steam generator lower assemblies, the welds must be coated with a~heavy bodied varnish such a tol (3.2.6).(k)If credit for the unplugged conf'.ation of the repaired steam generators is to be taken, new ECCS analysis using the approved model will be r'red (3.3.1).DELETED K.~OEL'E fED 1.The Plan for Integrated Scheduling of Plant Modifications for Turkey point Units 3 a 4 (the Plan), mitted on December 19, 1986, is approved.Plan shall be followed by the licensee from and a the effective date of this amendment.

b.Changes to s f or completion o f i tems identified in Sch le B do not require a licensee amendment.

Dat pecified'in Schedule A shall be changed only z accordance with applicable NRC procedures.

This license condition shall be effective til December 31, 1991, subject to renewal upon applicatio by the licensee.L.The license shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provision o f the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822)and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Turkey Point Plant, Units 3 and 4 Security Plan," with revisions submitted through April 13, 1988;"Turkey Point Plant, Units 3 and 4, Training and Qualification Plan," with revisions submitted through December 18, 1986;and"Turkey Point Plant, Units 3 and 4 Safeguards Contingency Plan," with revisions submitted through July 15, 1985.Changes made in L.l-3 1 I DPR-3 1 Page 8 accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.all proceed with implementation of the recommendations set forth in raphs 7b and c of the"Summary and Conclusions" section of the" i vironmental Statement Related to Operation of Turkey Point, Florida and Light Company, Docket Nos.50-250 and 50-251, issued July by the AEC Directorate of Licensing.

No later than thirty (3 from the date of issuance of this license, FPL shall submit to t for review and approval, its plan f or the implementation such recommendations.

This license is effective as of the date of issuance, and shall expire at midnight July 19, 2012.

I DPR-41 Page 5 F.FPL shall implement and mhintain in effect all provisions of the approved Fire Protection Program-as described in the Updated Final Safety Analysis Report (UFSAR)for Turkey Point Units 3 and 4 and as approved in the Safety Evaluation Report (SER)dated March 21, 1979 and supplemented by NRC letters dated April 3, 1980, July 9, 1980, December 8, 1980, January 26, 1981, May 10, 1982, March 27, 1984, April 16, 1984, August 12, 1987, and by Safety Evaluation dated February 25, 1994, subject to the following provision.

The licensee may make changes to the approved Fire Protection Program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.DELETED H.(1)The Turkey Point Plant steam generator repair program as described in the licensee's"Steam Generator Repair Report" dated September 20, 1977, as supplemented on December 20, 1977, March 7, April 25, June 20 and August 4, 1978, January 26, 1979 and March 28, 1980, and the affidavit of A.J.Gould dated June 12, 1981, for Unit No.4 is approved pursuant tothe Atomic fety and Licensing Board Final Order dated June 19, 198 (2)During e repair program the following temporary license co itions*will be imposed: (a)All fuel hall be removed from the reactor pressure ve el of the unit under repair and stored in the ent fuel pool.(b)The health physics ogram and procedures which have been establishe for the steam generator repair program shall be lemented.(c)Progress reports shall be ovided at 60-day intervals from the start of the air program and due 30 days after close of the int al with a*References in parentheses refer to the Safety Evaluation eport (NUREG-0756)

December 1980.

t DPR-41 ge-6 final report provided within 60 days after completion of the repair.These reports will include: A summary of the occupation exposure expended to date using the format and detail of Table 3.3-2 of the"Steam Generator Repair Report" as supplemented.(ii)An evaluation of the effectiveness of dose reduction techniques as specified in Section 3.3.5 of the"Steam Generator Repair Report" as supplemented in reducing occupational exposures.(iii)An estimate of radioactivity released in both liquid and gaseous effluents.(iv)estimate of the solid radioactive w te generated during the repair effort in uding volume and radioactive content.(d)Procedures sha be prepared to assure that power can be restored y manual operator actions to the fuel pool of th unit undergoing repair within eight hours (3.2.2.2).(e)The remedy chosen by FPL to provide the availability of the d esel fuel supply while the oil-retention dike is r oved from the main diesel safety tank shall be ddressed and adequately demonstrated by FPL pr'or to initiating the construction changes affect g the dike (3.2.2.2).(f)Sixty days prior to fuel loa'ng, the program for preoperational testing and startup shall be submitted for NRC review (2.7).(g)Sixty days prior to fuel loading, L should submit for evaluation by the NRC a s earn generator secondary water chemistry control a d monitoring program (3.2.4)which will address th following:

Identification of a sampling s edule for the critical parameters and o control points for these parameters for e ch mode of operation:

normal operatio , hot startup, cold startup, hot shutdown, cold wet layup;(ii)Identification of the procedures used o measure the values of the'ritica parameters; t DPR-41 Page 7 (iii)Edenti f ication of process sampling points;(iv)Procedure for-the recording and management of data;(v)Procedures defining corrective actions*for off-control point chemistry conditions; and (vi)A procedure identifying (a)the authority responsible for the interpretation of the data and (b)the sequence and timing of administrative events required to initiate corrective action.FPL ould verify that the steam generator secondary water emistry control program incorporates technical recomme ations of the NSSS vendor.Any significant deviation from NSSS vendor recommendations should be noted and stified technically.(h)Sixty days p'or to the decontamination of the channel head, FPL shou meet the following conditions (3.2.5): A system should be set up so that the pressure in the i flatable plug seal in the RCS pipe nozzles sh ld be monitored.

Upon loss of seal pressure, i'ection of the grit slurry should be stopped'diately and the seal plug replaced.Written pro dures should be provided to include acco tability controls of all tools, equipm , materials, and supplies ,that are to be ed in the channel heads to prevent inad ertent entry of such items into the re ctor primary coolant system.These co rois should be in effect whenever the i latable plug seals and their associated co er plates are not in place in the nozzle of the reactor coolant system piping.*Branch Technical Position MTEB 5-3 describes the acceptab e means for monitoring secondary side water chemistry in PWR steam generators, including corrective actions for off-control oint chemistry conditions.

However, the staff is amenable to alternatives, particularly to Branch Technical Position B.3.b)of MTEB 5-3 (96-hour time limit to repair or plug confirm condenser tube leaks).

DPR-41 Page 8 (iii)Written procedures should be provided to restrict materials to be used in the channel head area to prevent the presence of materials having potential adverse effects on the reactor coolant system components (for example, chloride-bearing

'materials)

.(iv)Written procedures should be provided to include instructions to require that the channel head area, including the nozzles, be inspected and confirmed to be free of all loose materials, equipment, and tools prior to removing the cover plate from the inflatable plug seal.(v)Prior to closing up the reactor coolant'system nd starting the RCS pumps, any loose debris, i luding the abrasive grits, in the channel hea RCS hot leg, and cold leg-should be clean d up.(vi)Pr r to resumption of power operation, the'censee should submit for NRC review'and a ceptance a report which will include an analysis of the possible effects o any foreign material which has entered the primary coolant system and has not be retrieved.

The report should inclu all work on the decontamination and steam generator repair.(i)Sixty days prior to the movement the used steam generator lower assemblies from the ntainment, the procedures for the move, associated QA re irements, and a description of the equipment'to be u d shall be provided to the NRC (3.2.6).(j)Before storage or shipment of the used steam g erator lower assemblies, the seal welds must be coated'th a heavy bodied varnish such as glyptol (3.2.6).(k)If credit for the unplugged configuration of the repaire steam generators is to be taken, a new ECCS analysis using the approved model will be required (3.3.1).DELETED DELETED I DPR-41 Page 9 K.1.The Plan for Integrated Scheduling-of Plant Modifications for Turkey Point Units 3&4 (the Plan), submitted on er 19, 1986, is approved.a.The shall be followed by the licensee from and after the ective date of this amendment.

b.Changes to dates fo mpletion of items identified in Schedule B do not re're a licensee amendment.

Dates specified in Schedule all be changed only in accordance with applicable NR rocedures.

This license condition shall be effective unti cember 31, 1991, subject to renewal upon application by e licensee.L.The license shall fully implement and maintain in.effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provision of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822)and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Turkey Point Plant, Units 3 and 4 Security Plan," with revisions submitted through April 13, 1988;"Turkey Point Plant, Units 3 and 4, Training and Qualification Plan," with revisions submi t ted through December 18, 1986;and"Turkey Point Plant, Units 3 and 4 Safeguards Contingency Plan, with revisions submitted through July 15, 1985.Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.This license is effective as of the date of issuance, and shall expire at midnight April 10, 2013.

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AOMINI STRATI VE CONTROLS COMPOS'ITION 6.5.1.2 The PHSC shall have a minimum of nine voting members and be composed of individuals from each of the following disciplines:

Operations

~~~Maintenance Health Physics Reactor Engineering ProMkfon Services Technical Support Licensing guality Assurance/Control Instrument and Control The PNSC Chairman and Vice-Chairman shall be appointed in.writing from among the members by the Plant General Manager.'he members, according to individual job titles, shall meet the requirements as described in Sections 4.2, 4.3, or 4.4, of the ANSI N-18.1" 1971.ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the-Plant General Manager to serve on a temporary basis;however, no more than two alternates shall participate as members in PNSC activities at any one time.MEETING FRE UENCY 6.5.1.4 The PNSC shall meet at least once per calendar month and as convened by the PNSC Chairman or his designated alternate.

gUORUM 6.5.1.5 The quorum of the PHSC necessary for the performance of the PNSC responsibility and authority provisions of these Technical Specifications shall consist of the'Chairman or Vice Chairman and four members including alternates.

RESPONSIBILITIES 6.5.1.6 The PNSC shall be responsible for: Review of all safety-related plant administrative procedures and changes thereto.b.C.d.Review of all proposed tests and experiments that affect nuclear safety;Review of all proposed changes to Appendix"A" Technical Specifications; Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety;TURKEY POINT" UNITS 3 8(4 6-6 AMEHDMEHT NOS.153 AND 148, 0 ADMINISTRATIVE CONTROLS RECORDS 6.5.2.9 Records of CNRB activities shall be prepared, approved, and dis-tributed as indicated below: a.Minutes of each CNRB meeting shall be prepared, approved, and forwarded to the President-Nuclear Division within 14 days follow-ing each meeting;b.Reports of reviews encompassed by Specification 6.5.2.7 shall be prepared, approved, and forwarded to the President-Nuclear Division within 14 days following completion of the review;a'nd C.Audit reports encompassed by Specification 6.5.2.8 shall be forwarded to the President"Nuclear Division and to the management positions responsible for the areas audited within 30 days after completion of the audit by.the auditing organization.

6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.3.1 Activities that affect nuclear safety shall be conducted as follows: a.Procedures required by Specification 6.8, and other procedures that affect nuclear safety, and changes thereto, shall be prepared, reviewed, and approved;Each such procedure, or change thereto, shall be reviewed by an individual/group other than the individual/

group who prepared the procedure, or change thereto, but who may be from the same organization as the individual/group who prepared the procedure, or change thereto.Procedures other than plant admin-istrative procedures shall be approved by the Plant General Manager, Operations Manager, or the head of the department assigned responsi-bility for those procedures prior to implementation.

The Plant General Manager shall approve plant administrative procedures and emergency plan implementing procedures.

Security Plan and the implementing procedures shall be approved b ervices Manager prior to implementation.

Changes to procedures hat may involve a change to the intent of the original procedures shall be approved by the individual authorized to approve the pro edure prior to implementa-tion of the change.~%PIC Ck d<TURKEY POINT-UNITS 3 6 4 6-11 AMENDMENT NOS.)53 AND 148, 4~v