ML20037D282

Amends 69 & 61 to Licenses DPR-31 & DPR-41,respectively, Approving Steam Generator Repair Program & Providing License Conditions Re Repair Operation

ML20037D282
Person / Time
Site:	Turkey Point
Issue date:	06/24/1981
From:	Eisenhut D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20037D283	List: ML20037D282 ML20037D285
References
NUDOCS 8107090249
Download: ML20037D282 (19)

Text

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==C Aj FLORICA POWER AMD LIGe. T COMPANY DOCKET NO:-SO-250 TURKEY POINT NUCLEAR GENERATING UNIT NO. 3-AMENDMENT TO FACILITY OPEP.ATING LICENSE Amendment No. 69 License No. DPR-31 ~ 1. 'The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by Florida Power and Light Company as supplemented December 20, (the licensee) dated September 20, 19776 March 7, April 25, June 20 and August 4,1978, January 26,1979 and March 28,1980. complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the appli. cation, the-provisions of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; C. There is reasonable assurance (i) that the activities authorized l by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and l E. The issuance of this ~ amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied. 2. Accordingly, Facility Operating License No. DPR-31 is hereby amended by adding a new paragraph 3.1 as follows: 3.I Steam Generator Reoair Proaram 1 l (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, March 7, April 25, June 20 and August 4,1978, l January 26, 1979 and March 28, 1980, and the affidavit of A. J. Gould dated June 17., 1981, for Unit No. 3 is approved pursuant to the Atomic Safety and Licensing Board' Final Order dated June 19, 1981 1 8107090249 810624 PDR ADOCK 05000250 P PDR

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1. 3 (2) 'During the~ repair program the following temporary license conditions

• will be imposed:

(~a) All fuel :h:11 he removed from the reactor pressure vessel of tne unit uncer repair'and stored in the spent fuel pool. (b) The health physics program and procedures which have been estaoiished for the steam generator repair program shall bs implamanted. (c) Progress reports shall be provided at 60-day intervals from the start of the repair program and due 30 days after cl'se of the interval with a final report provided within 60 day after completion of the repair. These reports will include: (i) A summary of the occupation exposure expended to date using the format and detail of Table 3.3-2 of i.ne " Steam Generator Repair Report" as supple'mented. (ii) An evaluation of the effectiveness of dose reduction techniques as specifieIt 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 gaseou; effluents. (iv) An estimate of the solid radioactive waste generated during the repair effort including volume and radioactive content. (d) Procedures shall be prepared to assure that power can be restored ~ by manual operator actions to the fuel pool of the unit under-l going 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 safety tank shall be addressed and adequately demonstrated by FPL prior to initiating the construction changes affecting the dike (3.2.2.2). (f) Sixty days prior to fuel loading; the program for preoperational testing and startup shall be submitted for NRC review (2.7). \\ f (g) Sixty days prior to fuel loading, FPL should submit for eval-uation by the NRC a steam generator secondary water chemistry control and monitoring program (3.2.4) which will address the I following:

• References in parentheses refer to the Safety Evaluation Report (NUREG-0756)

December 1980. 1 e.

1 . = " a., mMw.a (i) Identification of a sampling schcdule ' 'Aitical parameters and of control points for these parameters for each mode of operation: normal operation, hot _ startup, cold s.tartuo -not snutoown, cold wet layup; r s (ii) Identification Of the_ procedures used to measure +.he values of the critical oarameters; ~ (iii) ' Identification of proc.ess. sampling points; (iv) Procedure for the recording and management of data; (v) Procedures defining corrective actions

• for off-c ntrol 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 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): (i) 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 stopped immediately and the seal plug replaced. (ii) Written procedures should be provided to include account-ability controls of all tools, equipment, materials, and supplies that are to be used in the channel heads to prevent inadvertent entry of such items into the reactor primary coolant system. These controls should be in effect whenever the inflatable plug seals and their associated cover plates are not in place in the nozzles of the reactor coolant system piping - (iii) Written procedures should be provided to restrict materials g 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). l Position MTEB 5-3 describes the acceptable means for monitoring

• Branch Technica secondary side water chemi~stry in PWR steam generators, including corrective actions for off-control point chemistry conditions.

However, the staff is amenable.to, alternatives, particularly to Branch Technical Position B.3.b(9) of MTEB 5-3 (~ hour time limit to repair or. plug confirmed condenser tube leaks). .-._.7,.p.y ..-__7p,-.,.,._fp

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. + - - - - ~ - - ---- a. U (iv) 'n'rittsn procEduras shculd be provided to includF eum instructions to require that the channel head araa, including the n::uies, be inspected and confired to be free-o1Lall. loose materials, equioment, and tools prior to Ve=cving' the cover plate. from the inflatable ~ ~ - ~ plug :eal... (v) Prior to closing up the reactor coolant system and starting.._tne RCS pumps, any loose debris, inciuoing the abrasive grits, in the channel head, RCS hot leg, and cold leg should be cleaned up. (vi) Prior to resumption of power operation, the licensee should suomit for NRC review and acceptance a report which will include 'an analysis of the possible effects' of any foreign material which has entered the primary coolant system and has not been retrieveds The report should include all work on the decontamination and steam generator repair. (i) Sixty days prior to tne movement of the used steam generator lower assemblies from the containment, the procedures for the move, associated QA reouirements, and a description of the -equipment to be used shall be provided to the NRC (3.216). (j) Before storage or shipment of the used steam generator lowe,r assemblies, the seal welds must be coated with a heavy bodied varnish such as glyptol (3.2.6). (k) If credit for the unplugged configuration of the repaired steam generators is to be taken, a new ECCS analysis using the approved model will be required (3.3.1). 3. This license amendment is effective as of the date of its istuance. 0R THE NUCLEAR REGULATORY COMMISSION s 1 ~ u re i

Eisennut, re' tor Division of Licensing Office of Nuclear Reactor Regulation M 2 4 I38I Date of Issuance:

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f? **%q dy ' a.h UNITED STATES s, 8 *,.r, ( 3 % NUCLEAR REGULATORY COMMISSION a I h pp W AsHINGTON, D. C. 20555 g.mj FL5RIDA POWER AND LIGHT COMPANY DOCKET NO. ~ 50-251 TURKEY POINT NUCLEAR GENERATING UNIT NO. 4 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 61 License No. DPR-41 1. The Nuclear Regulatory Com~ mission (the Commission) has found that: A. The application for amendment by Florida Power and Light Company (the licensee) dated September 20, 1977, as supplemented December 20, March 7, April 25 June 20 and August 4,1978, January 26,1979 and r: March 28,1980, complies with the standards and reqairements of the Atomic Energy Act.of 1954, as amended (ttie Act) and the Commission's rules and regulations set forth in-10 CFR Chapter I; B. The facility will operate in confomity with the application, the provisions of the Ato.mic Energy Act of 1954, as amended (the Act) and the Commi.ssion's rules and regulations set forth in 10 CFR ChapterI;1,- C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the "public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 2. Accordingly, Facility Operating License No. DPR-41 is hereby amended ^ by adding a new paragraph 3.H as follows: 3.H SteamGeneratorRhoairProart.n g (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, 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 to the Atomic Safety and Licensing Board Final Order' dated June 19,19S1. .P

.o ~ .E-.--------------- ~ ;. -_4-_ .- u. u .m $R (2) During the repair progra= the_felleyjng temp rary license condition:= will ba imp; sed: -.2 (a) Ali fuci shcii be re=oved fri: the reactor pressure vessel of the uni.t under repair.ano-storeo in tne spent fuel oool'. (b) The health physics progrs= :nd pr:c:dures which have been established for the steam generator repair program snail be imple aented. (c) progress recorts shall be provided at 60-day intervals from the ~ start of the repair program and due 30 days after close of the interval with a final report provided within 60 days after completion of the repair. These reports will include: (i) 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. I (ii) An evaluation of the effectiveness of dose reduction techniques as specifie-d in Section 3.3.5 of the " Steam Generator Repair Report" as supplemented in reducing occupational exposures. (iii) An estir; ate of radioactivity released in bcth Iiquid and gaseous effluents. (iv) An estimate of the solid radioactive waste generated during the repair effort including volume and radioactive content. (d) Procedures shall be prepared to assure that power can be restored by manual operator actions to the fuel pool of the unit under-goyg repair within eight hours (3.2.2.2). (e) The remedy chosen by FPL to provide the availability of the diesel fu&l supply while the oil-retention dike is removed from the main diesel safety tank shall be addressed and adequately demonstrated by FPL prior to initiating the construction changes affecting the dike (3.2.9.2). (f) Sixty days prior to fuel loading, the program for preoperationc! testing and startup shall be submitted for NRC review (2.7). (g) Sixty days prior to fuel loading, FPL should submit for eval-uation by the NRC a steam generator secondary water chemistry l control and monitoring program (3.2.4) which will address the following:

• References in parentheses refer to the Safety Evaluation Report (NUREG-0756)

December 1980.

^ _m._. z =_ _ _.. 3 v-:. ~.. $. ~._, Identific: tion f c s:=pling schedule fer the critical U (i) paramatars and of control points for these para Eters f r each.:cde of operation: normal operatiun, but .startuo, coio startup, not sr.utoown, colo wet.iayup; (ii) Identift::ti:n cf the precedures used to measure the vaiues of tne critical parameters; (iii) Identification 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) th' authority responsible for the interpretation of the data and (b) the sequence and timing of administrative events required to initir:e corrective action. 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 th'e channel head, FPL should meet the following conditions (3.2.5): ~ (i) A system should be set up so that the pressure in the inflatable plug seal in the P.CS pipe nozzles should be monitored. Upon loss of seal pressure, is section of the grit slurry should be stopped immediately and the . seal plug replaced. j Written procedures should be provided to include account-(ii). ability controls of all tools, equipment, materials, and supplies that are to be used in the channel heads to prevent inadvertent entry of such items into the reactor primary coolant system. These controls should N in effect whenever the ir.flatable plug seals and their associated cover plates are not in pl. ace in the nozzles of the reactor coolant system piping. (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-c bearing materials).

• 5 ranch Technical Position 14TEB 5-3 describes the acceptable me'ans for monitoring secondary side water chemistry in FWR steam generators, including corrective actions for off-control point chemistry conditions.

However, the staff is amenabre. to. alternatives, particularly to Branch Technical Position B.3.b(9) of V.TEB 5-3 (95-hour time limit to repair or ' plug confirmed condenser tube leaks). l l

_q .= .mm. m. a -4< - -= " =. (iv) '.'ritten pre:cdures sh:uld Ee pr tidad t: f r.:1ude ~ instructions to require that the channal haad trc:, ~~ i~ncludina the nozzies, be inspected and confimed to ~ ~~~~~ ~ ~ ^ be free of ~all loose materials,' equipment, and tools s prior to removing the cover plate fro'n the inflatable plug seal. _. _ v) Prior to closing up the reactor _ coolant system and ( starting the RCS pumps, any loose debris, including the abrasive grits, in the channel head, RCS hot leg, and cold leg should be cleaned up. (vi) Prior to resumption of power operation, the licensee report should sutsnit for NRC review and accept' nea o which will include an-analysis of the possible effects of any foreign material which has entered the primary coolant system and ha' not been retrieved. The' report s should include all work on the decontaminati. : and steam generator repai g, (i) Sixty days prior to the movement of the used steam generator 1:wer assemblies from the containment, the procedures for the move, associated QA requirements, and a description of' the equipment'to be used shall be provided to the NRC (3.2.6)., (j) Before storage or shipment of the used steam generator lower assemblies, the seal welds must be coated with a heavy bodied varnish such as glyptol (3.2.6). (k) If credit for the unplugged configuration of the repaired steam generators is to be taken, a new ECCS analysis using the. approved model will be required (3.3.1).., 3. This license amendment is effective as of the date of its issuance. FOR THE NUCLEAR REGULATORY COMMISSION ~ DarrellG.hisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Date of Issuance: JUN 2 41981 l 1

f. {. s-y, i. .:4 .. a.u -, t E,, ATTACHMErlT TO LICitdf hENDMENT 3 AttE!!O"E!:T ?:0. 59 TO FACILIU OPEP.AT!"G LICENSE NO. DPP.-31 ,,a..._ .e e uv

r.... v, so-csu Replace the following pages of Facility Operating License No. DPR-31 witn the attacned pages as indicated. The changed area in the license is indicated by a marginal line.

~~ ~ ~ ~ Remove Pages Insert Pages 5 5 l 6 6 7 8 9 9 4 8 9 9 9 a

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. -. = a 5. 3. Fi e Pmtection Tha licensee may p ::S$d-with and is required to provide a schedule for and to compTete the ' modifications idar...... Paragraphs 3.1.1 thr: ugh 3.1.19 of the NRC's Fire Protection i Safety Evaluation, dated March 21, 1979 for the facility. These modifications are t.o be completed prior to Osccmb:r 1920. If any modifications :anr.ot be completed on schedule the licensee shall submit a report explaining the circumstances together_with a revised schedule. In addition, the licensee shall submit the additional information identified in Sections 3.1 and 3.2 of the related Safety Evaluation in accordance with the schedule contained herein. In the event these dates for submittal cannot be met, the licensee shall submi: a report, explaining the circumstances, together with a revised schedule. The licensee is required to develop and! implement the administrative controls which are consistent with the licensee's letters of August 28 and November 7,1978 within three months"from the date of this amendment. H. Safeauards Continoency Plan The licensee shall fully implemer.t and maintain in effect all provisions of the Commission-approved Safeguards Contingency Plan, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p). The approved Contingency Plan consists of documents withheld from public disclosure pursuant to 10 CFR 2.790(d) and identified as "Tu'rkey Point Plant Safeguards Contingency Plan" dated June 17, 1980 and submitted The Contingency Plan shall be fully implenmnted, pursuant to 10 CFR 73.40. in accordance with 10 CFR 73.40(b), within 30 days of this approval. I. Steam Generato'r Recair Procram (1) The Turkey Poin't Plant steam generator repair program, as described in the licensee's " Steam Generator Repair Report" dated September 20, 1977, as suppleme'nted.on December 20, 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 i's approved pursuant to the Atomic Safety and Licensing Board Final Order dated June 19, 1981 g (2) During the repair program the following temporary license conditions

• will be imposed:
• References in parentheses refer to the Safe'ty Evaluation Report (NUREG-0756)

December 1980.

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~ -s-i-1;. d a. E-a (a) All fuel-snali. Le removed from.tne xaactor. pressure vessel of the unit undar repair and stored in Ine spent fuel pool. = O) _Tht h alth physics program and p c56:res which have been i established for the steam generator re: air program shall be 2 - implemented. (c) Progress reports shall be. provided at 60-day intervals from the . start of the repair program and due 30 days after close of the interval with a final report provided within 60 days after completion of the repair. These reports will inciude: (1) A summary of the occupatico exposure expended to date using the format and detail of Table 3.3-2 of the " Steam Generator Repair Report" as supplemented. (ii) An evalua.lon 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. 9 (iv)- An estimate of the solid radioactive waste generated during.the repair effort including volume and radioactive content. (d) Procedures shall be prepared to assure that power can be restored i by manual operator actions to the fuel pool of the unit urder-going 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 dikh is removed from the main diesel safety tank shall be addressed and adequately demonstrated by FPL prior to initiating ue construction changes affecting the dike (3.2.2.2). (f) Sixty days prior to fuel loading, the program for preoperational testing and startup shall be submitted for NRC review (2.7). (g) Sixty days prior to fuel loading, FPL should submit for eval-untion by the NRC a steam generator secondary water chemistry control and monitoring program (3.2.4) which will address the t following: .+ 4 ,.i - - - v ---=-,.-,--y, ,.-,-,-e -,a.- ..e e-e .r w ,i,.e. -,.,.-e-v=e,n.v. -,.. - -y y-.m,--,-., ..,,- - - -,,--rw--. m.-v,---,

o ..i .__t.'__ 3_ ,. u_ h, y. _ _..._. ' 4 W w.- u a_ r . w_wl.' r ...; >:~ ^i .2+. ( V w. tie:., _ __ -.a (i) Identifica-ion of a.sampiing scnecula for the criticai.. para =eter'., and of centrol points for tnese parameters for each mode of operation: nomal operation, hot --~. _n.. _ stam;MOEQ p.. het -Ohttd0wn. 001d wet 1., (ii) Identification of the procedures used to measure the values of the critical parameters; (iii) Identification.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 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 charnel head, FPL should meet the following conditions (3.2.5): 1 l (1) 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 l the grit slurry should be stopped immediately andsthe seal plug replaced. (ii) Written procedures should be provided to include account-ability controls of all tools, equipment, materials, and supplies that are to be used in the channel heads to l prevent inadvertent entry of such. items into the reactor l primary coolant system. These controls should be in effect whenever the inflatable plug seals and their associated cover plates are not in place in the nozzles of the reactor coolant system piping. ' (iii) Written procedures should be provided to restrict materials s to be used in the channel head area to prevent the presence l of materials having potential adverse effects on the i reactor coolant system components (for. example, chloride-l bearing materials).

• Branch Technical Position MTEB 5-3 describes the acceptable means for monitoring secondary side water chemi'stry in PWR steam generators, including corrective actions for off-control point chemistry conditions. However, the staff is amenable te alternatives, particularly to Branch Technical Position B.3.b(9) of f1ETB 5-3 (96-hour time limit to repair or plug confirmed condenser tube leaks).

l

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instructions t: require that the ch:nnel he:d 2rei. ' T^iincluding the nozzles, be inspactcd and confir=:d t: tree.or all loose materials, equipment, and tools na pFior to' removing the cover plate from the inflatable s .- plug seel. (v) ~1 Prior. to closing up the reactor cc0! ant system and starting the RCS pumps, any loose debris, including the ' abrasive grits, in the channel head', RCS hot leg, ^ and cold leg should be cleaned up. (vi) Frior to resumptien of power operation, the licensec should submit for NRC review and acceptance a report which will include an analysis of the possible effects of any foreign material which has entered the primary ccciar.t system and has not been retrieved. The report should include all work on the decontamination and steam generator repair. ~ (i) Sixty days prior to the movement of the used steam generator lower assemblies from the containment, the procedures for the move,' associated QA requirements, and a description of the equipment to be used shall be provided to the NRC (3.2.6). (j) Before storage or shipment of the used steam generator lower assemblies, the seal welds must be coated with a heavy bodied varnish such as glyptol (3.2.6). (k) If credit for the unplugged configuration of the repaired steam generators is to be taken, a new ECCS analysis using the approved model will be required (3.3.1). 4 FPL shall proceed with implementation of the recommendations set forth in paragraphs 7b and c of the " Summary and Conclusions" section of the i " Final Environmental Statement Related to Operation of Turkey Point i Plant, Florida Power and Light Company, Docket Nos. 50-250 and 50-251," issued July 1972 by the AEC Directs. ate of Licensing. No later than thirty (30) days from the date of issuance of this license, FPL shall submit to the AEC, for review and approval, its plan for the imple-mentation of such recommendations. 4 ev- .,-,,p ,-v--,, -,,,,..e, .,.------r-- e,

E -. -...... w.. 9.- -. - =. . z, 1 ?. s.~, " 5. Tnis license is effective as of the date of.issear.ca, and.shall exoire at midnight April 27, 2007. rr,,e... T. u. r...A.T. A.M.. T t.* C. W. C D.. r.* V. f.*f.1MM.T. C. C. T n. ni. '~ - Original signed by D. J. Skovholt for .J A. Giar.busso. Deputy Director for Reactor Projects Directorate of Licensing

Attachment:

Appendix A - Technical Specifications Date of Issuance: July 19,1972 0 at i o e e o 0 4 e O t l I f~ i I i 1

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.. w. .,a r.t. Ac.u..u.puf - re m.. c.r.u c. e. s urun_ ur_ t;T = = : ' - --- - - =- M AMENDMENT NO. 61 TO FACli.iTY GPERATING LICENSE t:0. DPR-41 DOCET NO. 50-251 Deplace the following pages of Facility Operating License No. DPR-41 with tha attached patas as indicated. The ch::;ed area in the license is indicated by a carginal line. Remove Paoes' Insert Pages l 7 7 8 9 10 f e e l e e o e O e --w----,-,.~m. ,r,-- ---w y.-.-,,-._.e_ ,,.~-w., ,,..--,.,-,-w,. c.y..y,y, -,,y-ry.,.,,- -,--we .-.--r-.,y e,y,,-,

s O 7-1 ;... H. Steam Generator Repair Procram - ' = ~ (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, March 7, April 25, June 20 and August 4,1978, 7 Janua ry 26, 1979 and March 28, 1980, and the -affidavit of ' A. J. Gould dated June 12, 1981, for Unit No. 4 is approved ~... pursuant to the Atomic Safety and Licensing Board Final - Order dated June 19, 1981. (2) During the repair program the following temporary license conditions *' will be imposed: ~ (a) All fuel shall be removed from the reactor pressure vessel of the unit under repair and stored in the~ spqnt fuel pool.. (b) The health physics program and procedures which have been establis,hed for the steam generetor repair program shall be impl emented. (c). Progress reports shall be provided at 60-day intervals from the start of the repair program and due 30 days after close of the interval with a final report provided within 60 days after ' completion of the repair. These reports will include: (i) 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 in id and gaseous effluents. 2.. (iv) An estimate of the solid radioactive waste generated during the repair effort including volum,e and radioactive content.. I (d) Procedures shall be prepared to assure that power can be restored by manual ~ operator actions to the fuel pool of the unit under-going 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 safety tank shall be addressed and adequately demonstrated by FPL prior te initiating the construction changes affecting the dike (3.2.2.2).

• References in parentheses refer to the Safety Evaluation Report (NUREG-0755)

December 1980.

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z=- = n.8 n-e - -- -..... - =.. {g-(f) Sixty days'pri:r t: f:M::dir.g, the ; :grs= for preeperatienti ~ tasting and star, tup sh::11 bc : b=itted fer MP.C review (2.7). ~(g) ' Sixty dayFprior to fuel-loading [FPL shohld submit-for eval- ~ uatio.n by the NRC a steam senerator secondary water chemistry control and monitoring pr; gram (3.2.4)

• hich will address the following:

7 ~ ~ ~~ (i) Identification of a~~ sampling schedule for the critical parameters and of control points for these parameters for each mode of operation: nomal operation, hot.. _ startup, cold startup, hot shutdown, cold wet layup; ~ Identification of the pro' edures used to measure the ~ (ii) c values of the critical. parameters; (iii) Identification 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 tiniing of administrative events required to initiate corrective action. FPL should verify that the steam generator secondary water chemistry control program incorporates technf .>1 reconsnendations of the NSSS vendor. Any significant deviatbas from NSSS vendor recommendations should be noted and justified tech'nically. (h) Sixty days prior to the decontamination of the channel head, FPL should. meet the following conditions (3.2.5): (1) 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 stopped immediately and the seal plug replaced. i

• Branch Technical Position MTEB 5-3 describes t e accep at ble means for monitoring h

secondary side water chemistry in PWR steam generators, including corrective actions fcr off-control point chemistry conditions. However, the staff is amenable to alternatives, particularly to Branch Technical Position B.3.b(9) of MTEB 5-3 (96-hour time limit to repair or plug confirmed condenser tube leaks). v,- m- .,>,,--,,~-,,..w-.-,-e,e -e--e .---.,.ne-v e-,e-.s-r-,.--rv- -- - - - -, - ~.,-.~.=,,--.v.w-r-,,.--.v-,,w.m.,<.--mwwv.,s-vw*-wwwwn-e--e

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(ii). Writte pec:: dure: thould be previded to iMN4 account- - -aMiity controls of all te:1:, equip =ent, ~:sterials, and sdiUAiri Uist are to be used in tha channel h::d: t ..e - .orevent inadvertent entry of such items intG the raactor - -- -~ 'pfiiniff~ coolant system. These controls should be~1n - s effect wnenever, the inflatable plug seals and their associated cover plates are not in placa in tha nc::les of the reactor coolant. system piping. ~ ~ ~~ (iii) Written procedtires should be' provided to restrict materials to be used in the channel head area to prevent the presence of materiais having potential adverse effects on the reactor ecclant system components (for example, chloride-bearing materials). (iv) Written precedures should be provided to include ~ instructicas 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 rerming the caver plate from the inflatable plug seal. (v) Prior to closing up the reactor coolant system and - starting the RCS pumps, any loose debris, including the abrasive grits, in the channel head, RCS hot leg, and cold leg should be cleaned up. (vi) Prior to resump' tion' of power operation, the licensee should submit foi NRC review and acceptance a report l which will include an analysis of the possible effects of any foreign material which has entered the primary coolant system and has not been retrieved. The report should include all work on the decontamination and steam generator repair. (i) Sixty days. prior to the movement of the used steam generator lower assemblies from the containment, the procedures for the move, associated QA requirements, and a description of the equipment to be used shall be provided to' the NRC (3.2.6). l ~ Be' fore storage or shipment of the used steam generator lower (j) assemblies, the seal welds must be coated with a heavy bodied varnish such as glyptol (3.2.6). l (k) If credit for the unplugged configuration of the repaired steam generators is to be taken, a new ECCS analysis using the approved model will be required (3.3.1). i l --) w are .---.-m w e ---,.-e .r .,,,.e. -,.-v.-r~

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• • 4 This license is effecti se as of the date of issuance, and sr.all expire at midnight April 27, 2007.

.[._r~- _-.. _ _. _ _ _ FOR T}{E AT0".!O-C"C."0Y-00"".!!! ION ~ Original Signed By- ~ A. Gia=busso, De::::ty Director for Reactor Projects Directorate of Licensing Attachments: Appendix A - Technical Specifications Appendix B - En'vironmental Technical Specifications Date of Issuance: April 10,1973 O e 9 9 e I ,e I e l 4 i { -__. _ - _ _. _ - _,. _.....}}