ML17308A242

Rev 1 to Conformance to Reg Guide 1.97,St Lucie Plant,Units 1 & 2.

ML17308A242
Person / Time
Site:	Saint Lucie
Issue date:	05/31/1986
From:	Stoffel J EG&G IDAHO, INC.
To:	NRC
Shared Package
ML17216A646	List: ML17308A242
References
CON-FIN-A-6483, RTR-REGGD-01.097, RTR-REGGD-1.097 EGG-EA-6868, EGG-EA-6868-R01, EGG-EA-6868-R1, TAC-51135, NUDOCS 8607090516
Download: ML17308A242 (23)

Text

EGG-EA-6868 Revision 1 May 1986 INFORMALREPORT CONFORNNCE TO REGULATORY GUIDE 1.97, ST. LUCIE PLANT. UNIT NOS. 1 AND 2 J. M. Stoffe1 Prepared for the U. S. NUCLEAR REGULATORY CONNISSION

EGG-EA-6868 CONFORMANCE TO REGULATORY GUIDE 1.97 ST. LUCIE PLANT, UNIT NOS. 1 AND 2 J. M. Stoffel Pub11shed June 1986 EGLG Idaho, Inc.

Idaho Falls, Idaho 83415 Prepared. for the U.S. Nuclear Regulatory Comn1ss)on Mash1ngton, D.C. 20555 Under OOE Contract No. DE-AC07-76I001570 FIN'o. A6483

ABSTRACT Th1s EGLG Idaho, Inc., report rev1evs the subm1ttals for Rev1s1on 3 of Regulatory Gu1de 1.97 for Vn1t Nos. 1 and 2 of the St. Luc1e Plant and 1dent1f1es areas of nonconformance to the regulatory gu1de. Except1ons to Regulatory Gu1de 1.97 are evaluated and those areas ~here suff1c1ent bas1s for acceptab111ty 1s not prov1ded are 1dent1f1ed.

FOREMORO Th1s report 1s suppl1ed as part of the 'Program for Evaluat1ng Licensee/Appl1cant Conformance to RG 1.97," be1ng conducted for the U.S.

Nuclear Regulatory Coae1ss1on, Off1ce of Nuclear Reactor Regulat1on, D1v1s1on of PQR L1cens1ng-A, by EGEG Idaho, Inc., NRR and ICE Support Branch.

The U.S. Nuclear Regulatory Comn1ss1on funded the cwork under author1zat1on 20-19-10-11-3.

Docket Nos. 50-335 and 50-389 TAC Nos. 51135 and 5ll36 11

CONTENTS A BSTRACT ..............................................................

F OREWORD ..............................................................

1 INTRODUCTION

2. REVIEW REQUIREMENTS ......................-...............-.......

3 EVALUATION .......................................................

3.1 Adherence to Regulatory Gu1de 1.97 .........................

3 2

~ Type A Variables ...........................................

3.3 Exceptions to Regulatory Gu1de 1.97 ........................ 5 4 CONCLUSIONS ...................................................... 16 5 REFERENCES ....................................................... 17

CONFORMANCE TO REGULATORY GUIDE 1.97 ST. LUCIE PLANT UNIT NOS. l AND 2

l. INTRODUCTION On December 17, 1982, Gener1c Letter No. 82-33 (Reference l) was 1ssued by D. G. E1senhut, D1rector of the D1v1s1on of L1cens1ng, Nuclear Reactor Regulat1on, to all 11censees of operat1ng reactors, appl1cants for operat1ng 11censes and holders of construct1on perm1ts. Th1s letter 1ncluded add1t1onal clar1f1cat1on regard1ng Regulatory Gu1de 1.97, Rev1s1on 2 (Reference 2) relat1ng to the requ1rements for emergency response capab111ty. These requ1rements have been publ1shed as Supplement No. l to NUREG-0737, "THI Act1on Plan Requ1rements" (Reference 3).

Flor1da Power and L1ght Company, the 11censee for the St. Luc1e Plant, prov1ded responses to the Regulatory Gu1de 1.97 port1on of the gener1c letter on November 3O, 1983 (Reference 4), for Un1t No. 2, and on December 30, 1983 (Reference 5), for Vn1t No. l. Add1t1onal 1nformat1on was subm1tted on November 18, 1985 (Reference 6).

Th1s report prov1des an evaluat1on of those subm1ttals.

2. REVIEW REQUIREMENTS Sect1on 6.2 of NUREG-0737, Supplement No. l, sets forth the documentat1on to be subm1tted 1n a report to the NRC descr1b1ng how the 11censee compl1es w1th Regulatory Gu1de 1.97 as appl1ed to emergency response fac111t1es. The subm1ttal should 1nclude documentat1on that prov1des the follow1ng 1nformat1on for each var1able sho~n 1n the appl1cable table of Regulatory Gu1de 1.97.

l. Instrument range 2.. Env1ronmental qual1f1cat1on

3. Se1sm1c qual1f1cat1on

4. gual1ty assurance

5. Redundance and sensor locat1on

6. Power supply

7. Locat1on of d1splay

8. Schedule of 1nstallat1on or upgrade The subm1ttal should 1dent1fy dev1at1ons from the regulatory gu1de and prov1de support1ng ]ust1f1cat1on or alternat1ves.

Subsequent to the 1ssuance of the gener1c letter, the NRC held regional meet1ngs 1n February and )larch 1983, to answer 11censee and appl1cant quest1ons and concerns regard1ng the NRC pol1cy on th1s matter.

At these meet1ngs, 1t was noted that the NRC rev1ew would only address except1ons taken to Regulatory Gu1de 1.97. Where 11censees or appl1cants expl1c1tly state that 1nstrument systems conform to the regulatory gu1de, 1t was noted that no further staff rev1ew would be necessary. Therefore,

th1s report only addresses except1ons to Regulatory Gu1de 1.97. The follow1ng evaluat1on 1s an aud1t of the l1censee's subm1ttals based on the rev1ew pol1cy descr1bed 1n the NRC reg1onal meet1ngs.

3. EVALUATION The 11censee prov1ded. responses to the NRC Gener1c Letter 82-33 on November 30, 1983 and December 30, 1983 and add1t1onal 1nformat1on on November 18, 1985. Th1s evaluat1on 1s based on those subm1ttals.

3.l Adherence to Re ulator Gu1de 1.97 The l1censee stated that based on the 1nformat1on presented 1n the1r subm1ttals, the St. Luc1e Plant w1ll conform w1th the recoomendat1ons of Regulatory Gu1de 1.97, Rev1s1on 3 (Reference 7), by the end of the next refuel1ng outage (December 1985). Therefore, we conclude that the 11censee has prov1ded an expl1c1t comm1tment on conformance to Regulatory Gu1de 1.97. Except1ons to and dev1at1ons from the regulatory gu1de are noted 1n Sect1on. 3.3.

3.2 T e A Var1ables Regulatory Gu1de l.97 does not spec1f1cally 1dent1fy Type A var1ables, 1.e., those var1ables that prov1de the 1nformat1on requ1red to perm1t the control room operator to take spec1f1c manually controlled safety act1ons.

The 11censee class1f1es the follow1ng 1nstrumentat1on as Type A.

l. Pressur1zer pressure

2. Reactor coolant system (RCS) hot leg temperature

3. RCS cold leg temperature

4. Steam generator level (narrow range)

5. Conta1nment hydrogen concentrat1on Th1s 1nstrumentat1on meets the Category l recoaeendat1ons cons1stent w1th the requ1rements for Type A var1ables.

3.3 Exce t1ons to Re viator Gu1de 1.97 The 11censee 1dent1f1ed dev1at1ons and except1ons from Regulatory Gu1de 1.97. These are d1scussed 1n the follow1ng paragraphs.

3.3.l Neutron Flux The 11censee states 1n Reference 6 that two completely quallf1ed post acc1dent mon1tor1ng channels for th1s var1able have been 1nstalled 1n Un1t No. 2 dur1ng the last refuel1ng outage. Th1s same 1nstallat1on 1s be1ng 1nstalled 1n Un1t No. l dur1ng the then ex1st1ng refuel1ng outage.

These new channels comply w1th the recomnendat1ons of Regulatory Gu1de 1.97 for both range and qual1f1cat1on. Therefore, we conclude that the 1nstrumentat1on prov1ded for th1s var1able 1s adequate and acceptable.

3.3.2 Reactor Coolant S stem RCS Soluble Boron Concentrat1on Regulatory Gu1de 1.97 receanends cont1nuous read1ng 1nstrumentat1on w1th a range of 0 to 6000 parts per m1111on (PPH) for th1s var1able. The 11censee has prov1ded 1nstrumentat1on that covers ranges of 0 to 2050 PPH for Un1t No. l and a dual range of 0 to 1250/5000 PPH for Un1t No. 2. The 11cenSee ]ust1f1es these dev1at1ons by stat1ng that there are two add1t1onal boron concentrat1on measurement poss1b111t1es.

1. Manual grab sample

2. Post acc1dent sampl1ng system.

The 11censee dev1ates from Regulatory Gu1de 1.97 w1th respect to post-acc1dent sampl1ng capab111ty. 1'h1s dev1at1on goes beyond 'the scope of th1s rev1ew and 1s be1ng addressed by the NRC as part of the1r rev1ew of NUREG-0737, Item II.B.3.

3.3.3 RCS Hot 'Ke and Cold Le Mater Tem erature Regulatory Gu1de 1.97 recon+ends 1nstrumentat1on w1th a range of 50 to 700'F for th1s var1able. The l1censee, for Un1t No. l, prov1des 1nstrumentat1on w1th a range of 212'F to 705'F. The l1censee's

]ust1f1cat1on for th1s dev1at1on 1s that the purpose of RCS hot and cold leg temperature 1nd1cat1on 1s to determ1ne the RCS flu1d temperature to assure core heat 1s be1ng removed (hT between hot and cold leg temperature). For temperatures where the RCS temperature 1s below 350'F the shutdown cool1ng (SOC) system ~ould be 1n operat1on.

Mhen the SOC system 1s 1n operat1on, hot leg temperatures would be closely represented by the core ex1t thermocouples wh1ch have a range of 32'F to 2300'F and the cold leg temperatures would be closely represented by the SOC system temperature element wh1ch has a range of 0 to 400'F.

Based on the ava1lab111ty of alternate 1nstrumentat1on for determ1n1ng the hot and cold leg water temperatures below 212'F, we conclude that the 1nstrumentat1on prov1ded 1s adequate to mon1tor th1s var1able dur1ng post-acc1dent cond1t1ons.

3.3.4 RCS Pressure Pressur1zer Pressure The pressure range of the ex1st1ng 1nstrumentat1on 1s not as reconeended by Regulatory Gu1de 1.97 (0 to 4000 ps1g). The 1nstrumentat1on prov1ded covers a range of 0 to 3000 ps1g. The l1censee cons1ders the ex1sting range acceptable pend1ng the resolut1on of the ant1c1pated trans1ent w1thout scram (ATMS) 1ssue.

The ex1st1ng pressure range of 0 to 3000 ps1g 1s adequate to mon1tor all expected RCS pressures based on the acc1dent analys1s presented 1n the 11censee's F1nal Safety Analys1s Report (FSAR). The 11censee has made a coae1tment to 1nstall Category 1 1nstrumentat1on w1th a range 1n accordance w1th the resolut1on of the ATMS 1ssue, 1f pressures are found to exceed those currently presented 1n the FSAR. Therefore, we f1nd th1s dev1at1on acceptable.

3.3.5 Conta1nment Isolat1on Valve Pos1t1on From the 1nformat1on prov1ded, we f1nd the l1censee dev1ates from a str1ct 1nterpretat1on of the Category l redundancy recooeendat1on. Only the act1ve valves have pos1t1on 1nd1cat1on (1.e., check valves have no pos1t1on 1nd1cat1on). S1nce redundant 1solat1on valves are prov1ded, we f1nd that redundant 1nd1cat1on per valve 1s not 1ntended by the regulatory gu1de. Pos1t1on 1nd1cat1on of check valves 1s spec1f1cally excluded by Table 3 of Regulatory Guide 1.97. Therefore, we f1nd that the 1nstrumentat1on for th1s var1able 1s acceptable.

3.3.6 Rad1at1on Level 1n C1rculat1n Pr1mar Coolant In Reference 6, the 11censee states that rad1at1on level measurements to 1nd1cate fuel cladd1ng fa1lure are prov1ded by the post-acc1dent sampl1ng system, wh1ch 1s be1ng rev1ewed by the NRC as part of the1r rev1ew of NUREG-0737, Item II.B.3.

Based 'on the alternate 1nstrumentat1on prov1ded by the 11censee, we conclude that the 1nstrumentat1on suppl1ed for th1s var1able 1s adequate and, therefore, acceptable.

3.3.7 Accumulator Tank Level and Pressure The 11censee has 1nstrumentat1on that does not meet the follow1ng recomnendat1ons of Regulatory Gu1de 1.97: (a) the level range for Un1t 1 (10 to 90 percent volume), (b) the pressure range (0 to 750 ps1g), or (c) the env1ronmental qual1f1cat1on for these var1ables.

The 11censee states that the Un1t No. l level range 1s 20 to 60 percent volume and that th1s 1s necessary to ma1nta1n the techn1cal spec1f1cat1on requ1red level. The h1gh and low alarm setpo1nts are 3 percent of the ex1st1ng range apart. The water level must be ma1nta1ned w1th1n th1s narrow span. Expand1ng the range would decrease the 1nstrument accuracy, caus1ng operator d1ff1culty and alarm recogn1t1on problems.

Me conclude that the ex1st1ng level range for Un1t No. l 1s acceptable.

The licensee states that the Un1t l pressure range 1s 0 to 300 psig.

Their )ustification for this dev1at1on 1s that the safety in]ection tanks are designed for 300 ps1g. S1nce the tank pressure requ1red by the plant technical specif1cations 1s 200 to 250 psig and the pressure is manually mainta1ned, we f1nd that the installed range 1s adequate. Therefore, th1s is an acceptable dev1at1on from Regulatory Guide 1.97.

The licensee states that the Un1t 2 pressure range 1s 0 to 700 psig.

Their )ustification for this dev1at1on 1s that 700 ps1g exceeds the tank design pressure and the tank safety valve setpoint. Since the tank pressure required by the plant techn1cal spec1f1cat1ons 1s 600 to 625 ps1g and the pressure 1s manually mainta1ned, we find that the range 1s adequate. Therefore, th1s range is an acceptable dev1ation from Regulatory Gu1de 1.97.

The 11censee takes except1on to the env1ronmental qualification that 1s recomnended by the gu1de for these variables and.states that the sensor is located 1n a harsh env1ronment post-acc1dent. The licensee states that th1s var1able 1s not requ1red to perform a safety funct1on or to m1tigate the consequences of an accident. It is prov1ded for plant surveillance dur1ng normal operation.

The ex1st1ng instrumentat1on 1s not acceptable. An env1ronmentally qualified instrument is necessary to mon1tor the status of these tanks.

The 11censee should des1gnate e1ther level or pressure as the key var1able to d1rectly 1nd1cate accumulator d1scharge and prov1de 1nstrumentat1on for that variable that meets the requirements of 10 CFR 50.49.

3.3.8 Refuelin Hater Stora e Tank Level Regulatory Gu1de 1.97 recoamends instrumentat1on w1th a range from the top to the bottom. The instrumentat1on covers a level range of 0 to 50 feet. The licensee states that th1s range covers the useful volume of

the tank (2.6 to 100 percent of the total tank he1ght). Me f1nd that th1s 1nstrumentat1on 1s adequate to mon1tor the operat1on of th1s storage tank.

Therefore, th1s 1s an acceptable dev1at1on.

3.3.9 Pressur1zer Level The pressur1zer level 1nstrumentat1on meets the Category l recommendat1ons of Regulatory Gu1de 1.97. However, Reference 4 and 5 1dent1f1ed the 1nstrumentat1on as be1ng narrow range 1nstead of the recommended range (top to bottom). In Reference 6 the 11censee states that th1s refers to the 1nstrument cal1brat1on range of 175 1nches to 349 1nches water column d1fferent1al pressure, wh1ch corresponds to w1de range pressur1zer level when the pressur1zer 1s at 650'F (1.e., hot cal1brated 1nstrumentat1on).-

Based on th1s add1t1onal 1nformat1on we conclude that the 1nstrumentat1on prov1ded for th1s var1able 1s adequate.

3.3.10 Pressur1zer Heater Status The 11censee has the recoaeended 1nstrumentat1on, but states 1n Reference 5 that only local 1nd1cat1on 1s prov1ded for Un1t No. l. In Reference 6 the 11censee states that 1n add1t1on to the local current 1nd1cat1on for pressur1zer heaters, Un1t No. l has control room 1nd1cat1on of pressur1zer heater k1lowatts.

The k1lowatts of power used by the pressur1zer heaters has a d1rect relat1on to the heater current. Based on our rev1ew and ]udgment, we f1nd th1s dev1at1on of measur1ng pressur1zer heater 1nput po~er rather than current acceptable, s1nce the heater power has a known relat1on to the heater current.

Regulatory Gu1de 1.97 recommends a range of top to bottom for th1s var1able. The 11censee has prov1ded 1nstrumentat1on that 1nd1cates 9.5 to 90.5 percent of the tank volume.

The level ma1nta1ned 1n th1s tank 1s approx1mately 60 percent of the total volume. The ex1st1ng low 11m1t of th1s 1nstrumentat1on 1s adequate to 1nsure that the sparger 1s covered and that suff1c1ent flu1d volume ex1sts to quench the des1gn bas1s steam release. The ex1st1ng h1gh 11m1t of th1s 1nstrumentat1on 1s adequate to 1nd1cate suff1c1ent gas volume to accept a pressur1zer steam release w1thout becom1ng overpressur1zed and to 1nd1cate 1n-leakage from the rel1ef d1scharge system, Based on th1s, we f1nd th1s 1nstrumentat1on adequate. Therefore, th1s dev1at1on 1s acceptable.

3.3.12 uench Tank Tem erature Regulatory Gu1de 1.97 recomends a range of 50 to 750'or th1s var1able. The 11censee has prov1ded 1nstrumentat1on w1th a range of 0 to 350'F. The'1censee states that th1s range 1s'acceptable based on the tank rupture d1sc caus1ng saturated steam cond1t1ons.

The range covers the ant1c1pated requ1rements for normal operat1on, ant1c1pated operational occurrences and acc1dent cond1t1ons. Th1s range relates to the tank's rupture disk that rel1eves pressure 1n excess of 85 ps1g. Th1s pressure rel1ef 11m1ts the temperature of the tank contents to saturated steam cond1t1ons of less than 350'F. Thus, we f1nd th1s dev1at1on from the regulatory gu1de a'cceptable.

3.3.13 Steam Generator Level The 11censee has narrow range steam generator level 1nstrumentat1on that meets the Category l recomnendat1ons of Regulatory Gu1de 1.97.

However, 1t does not meet the recomended level range tfrom tube sheet to 10

separators). A wide range non-safety channel 1s available and meets the recommended range, but it 1s not Category l 1nstrumentation.

The licensee's )ustificat1on for this dev1ation is that, in the event of an acc1dent, no operator action is cred1ted in the acc1dent analyses dur1ng the f1rst few m1nutes. Automatic act1on will protect the plant unt11 the operator can 1dentify the event using the existing instrumentat1on, and take appropriate action. In addition, the l1censee considers the qualified steam generator pressure 1nstruments to be the key var1able to determine the availab111ty of the steam generators as heat s1nks. Other instrumentat1on available to determ1ne steam generator ava1labil1ty are the auxiliary feedwater system pressure and flow instrumentation and the main feedwater flow 1nstrumentat1on.

The purpose of th1s variable 1s for the ident1f1cat1on and m1tigation of an accident and for determining the ava1lab111ty of the steam generators as heat s1nks. He find the licensee's )ustification for th1s dev1ation unacceptable. The level 1n the steam generator cannot be 1nferred from auxil1ary feedwater flow instrumentation ma1n feedwater flow instrumentat1on or steam generator pressure. The l1censee should provide env1ronmentally qual1fied wide range steam generator level 1nstrumentation for th1s variable.

3.3.14 Safet /Relief Valve Positions or Hain Steam Flow Regulatory Guide l.97 receanends Category 2 instrumentat1on for th1s variable. The 11censee uses steam flow instrumentat1on for this var1able that 1s not environmentally qual1fied. The. licensee states that the sensor 1s located in a harsh env1ronment post-accident. The licensee's equipment was prov1ded for plant surve1llance during normal operat1on and non-accident transients. The licensee states that th1s type of equipment has been generically qualified to a lesser environment than in-conta1nment acc1dent env1ronment for th1s plant. In Reference 6, the licensee states

that s1nce the.ma1n steam safety valves are outs1de conta1nment, and the ma1n steam flow 1nstrumentat1on 1s 1ns1de conta1nment, no env1ronmental qual1f1cat1on concern 1s present. For a ma1n steam l1ne break or loss of coolant acc1dent 1ns1de conta1nment, the env1ronmental qual1f1cat1on of the ma1n steam flow 1nstrumentat1on would be challenged. However, for th1s event, th1s 1nstrumentat1on would not prov1de any 1nput to any safety system, as the ma1n steam safety valves w1ll not be 11ft1ng. Should a safety valve 11ft, then there would be a normal env1ronment for the ma1n steam flow 1nstrumentation.

Due to the des1gn, w1th the ma1n steam safety valves outs1de of conta1nment, and the non-qual1f1ed ma1n steam flow sensors 1ns1de conta1nment, we f1nd the 1nstrumentat1on prov1ded for th1s var1able acceptable.

3.3.l5 Ha1n Feedwater Flow The 11censee has prov1ded 1nstrumentat1on for th1s var1able w1th a 6

range of 0 to 6 x 10 lb/hr. Regulatory Gu1de 1.97 recomnends 0 to 110 percent of des1gn flow for th1s var1able. The l1censee states that the 6

ex1st1ng range 1s close to the requ1red range'of 0 to 6.2 x 10 lb/hr, and that 1s 1s cons1dered adequate.

The ex1st1ng range w1ll adequately mon1tor the operat1on of th1s system 1n post-acc1dent cond1t1ons. Therefore, th1s 1s an acceptable dev1at1on from Regulatory Gu1de 1.97.

3.3.16 Heat Removal b the Conta1nment Fan Heat Removal S stem The 11censee takes except1on to the env1ronmental qual1f1cat1on (Category 2) receanended by Regulatory Gu1de 1.97 for h1s var1able. The l1censee states that the thermocouple assembl1es have been purchased as non-safety equ1pment and that they do not perform a safety funct1on dur1ng or after an acc1dent. The 11censee states that after an acc1dent, all four 12

containment fan coolers are started and r'ema1n operat1onal, The conta1nment atmosphere temperature instrumentat1on 1s env1ronmentally qual1f1ed and provides information on conta1nment temperature.

We f1nd the 11censee's )ustification for th1s dev1at1on unacceptable.

Conta1nment atmosphere temperature instrumentatlon cannot adequately monitor the proper operation of the containment fan heat removal system.

The licensee should prov1de environmentally qual1f1ed instrumentat1on for th1s var1able.

3.3.17 Containment Atmos here Tem erature Vn1t l onl Regulatory Gu1de 1.97 recommends instrumentat1on w1th a range to 400'F for th1s variable: The l1censee has prov1ded instrumentat1on w1th a range to 350'F. The 11censee states that the range provided is adequate because the maximum ma1n steaml1ne break .(HSLB) temperature is 290'F.

S1nce the max1mum expected temperature occurs after a HSLB, we cons1der th1s temperature range adequate to monitor normal, operat1ng and accident temperatures 1n the containment. Therefore, this is an acceptable dev1ation from Regulatory Gu1de l.97.

3.3.18 Letdown Flow-Out Vn1t 1 onl Regulatory Gu1de 1.97 recomaends a range of 0 to ll0 percent of design flow for this variable. The des1gn flow at th1s un1t 1s 132 GPH. The licensee has provided instrumentat1on with a range of 0 to 140 GPH (106 percent of design flow).

Although the installed range does not comply w1th the gu1dance of Regulatory Guide 1.97, considering 1ts use dur1ng and following an acc1dent, the ex1st1ng range is adequate. Therefore, this 1s an acceptable dev1at1on from Regulatory Gu1de 1.97.

3.3.19 Volume -Control Tank Level The 11censee, for Un1t No. 2, dev1ated from the range (top to bottom) and from the env1ronmental qual1f1cat1on recommended for th1s var1able.

The l1censee states that the ex1st1ng range covers 14.1 to 85.9 percent of the tank volume. In Reference 6, the 11censee states that the normal operat1ng range of th1s tank 1s 38 to 56 percent. Los and h1gh level control room annunc1at1on w111 not1fy the operator of any dev1atlon from th1s band.

The 11censee's )ust1f1cat1on 1nd1cates that the 1nstrumentat1on w111 rema1n on scale for any acc1dent cond1t1on. Therefore, ve f1nd th1s range dev1at1on acceptable.

The l1censee takes except1on to the env1ronmental qual1f1cat1on that, 1s recoamended by the regulatory gu1de for th1s var1able and states that the sensor 1s located 1n a harsh env1ronment post-acc1dent. In Reference 6 the l1censee states that the volume control tank 1s 1solated dur1ng an acc1dent and 1s 'not requ1red to perform a safety funct1on.

As th1s var1able 1s not ut111zed 1n con]unct1on v1th a safety system,

~e f1nd that the 1nstrumentat1on prov1ded 1s acceptable.

3.3.20 H1 h Level Rad1oact1ve L1 u1d Tank Level Regulatory Gu1de 1.97 recoamends 1nstrumentat1on for th1s tank that reads from top to bottom. The 1nd1cated range for th1s var1able corresponds to 5.2 to 93 percent of the tank volume.

Th1s range 1s adequate to 1nd1cate the storage volume dur1ng all acc14ent and post-acc1dent con41t1ons. Therefore, th1s 1s an acceptable dev1a t1on.

3.3.21 Rad1at1on Ex osure Rate 1ns1de bu1ld1n s or areas where access 1s re u1red to serv1ce e u1 ment 1m ortant to safet Regulatory Gu1de 1.97 recomnends Category 3 1nstrumentat1on w1th a range of 10

-l to 10 4 R/hr. The 11censee states that f1xed h1gh range area rad1at1on mon1tors located 1n areas 1mportant to safety w1ll not be useful to an operator; that personnel carry a portable h1gh range area detector on the tr1p to, at, and from the area 1mportant to safety. The 11censee states that there 1s a complete low range 'area rad1at1on mon1tor1ng system 1n the aux111ary bu1ld1ng. Reference 6 1dent1f1es the locat1on and range of the low range mon1tor1ng system. The range of these 1nstruments 1s 10 to l0 R/hr.

From a rad1o>g1cal standpo1nt, 1f the rad1at1on levels reach or exceed the upper 11m1t of the range, personnel would not be perm1tted 1nto the areas w1thout portable mon1tor1ng (except for l1fe sav1ng). Based on the alternate 1nstrumentat1on used by the 11censee for th1s var1able, we f1nd the proposed ranges for the rad1at1on exposure rate mon1tors acceptable.

3.3.22 Conta1nment or Pur e Effluent-Moble Gases Regulatory Gu1de 1.97 receanends a range of 10 to 10 uC1/cc for th1s var1able. The 11censee has prov1ded 1nstrumentat1on w1th a range

-8 of 8 x l0 to 5 x 10 4 yC1/cc. The 11censee states that the flow 1s d1luted, therefore, the ex1st1ng range 1s adequate.

The ex1st1ng range 1s adequate for detect1on of s1gn1f1cant releases and release assessment. The dev1at1on 1n the upper 11m1t of the range 1s m1nor. Therefore, th1s 1s an acceptable dev1at1on from Regulatory Gu1de 1.97.

3.3.23 Est1mat1on of Atmos her1c Stab111t Regulatory Gu1de 1.97 recomnends a temperature range of -9 to +18'F for th1s var1able. The 11censee has prov1ded 1nstrumentat1on with a range of -15 to +15'F, wh1ch 1s the d1fference between the 60 meter temperature and the 10 meter temperature.

Table l of Regulatory Gu1de 1.23 (Reference 8) prov1des seven atmospher1c stab1l1ty class1f1cat1ons based on the d1fference 1n temperature per 100 meters elevat1on change. These classlf1cat1ons range from extremely unstable to extremely stable. Any temperature d1fference greater than +4'C or less than -2'C does noth1ng to the stab111ty class1f1cat1on. The 11censee's 1nstrumentat1on 1ncludes th1s range.

Therefore, we f1nd that th1s 1nstrumentat1on 1s acceptable to determ1ne the atmospher1c stab1l1ty.

16

4. CONCLUSIONS Based on our rev1ew, we f1nd that the 11censee e1ther conforms to or 1s )ust1f1ed 1n dev1at1ng from Regulatory Gu1de l.97, w1th the follow1ng except1ons:

l. Accumulator tank level and pressure the 11censee'hould prov1de

'1ther level or pressure 1nstruments for .th1s var1able that are env1ronmentally qual1f1ed 1n accordance w1th 10 CFR 50.49.

(Sect1on 3.3.7).

2. Steam generator level the l1censee should prov1de w1de range level 1nstrumentat1on for th1s var1able that 1s env1ronmentally qual1f1ed 1n accordance w1th 10 CFR 50.49 (Sect1on 3.3.13).

3. Heat removal by the conta1nment fan heat removal system the 11censee should prov1de 1nstrumentat1on for th1s var1able that 1s env1ronmentally qual1f1ed 1n accordance w1th 10 CFR 50.49 (Sect1on 3.3.16).

17

5. REFERENCES

l. NRC letter, 0. G. E1senhut to All L1censees of Operat1ng Reactors, Appl1cants for Operat1ng L1censes, and Holders of Construct1on Perm1ts, "Supplement No. 1 to NUREG-0737 Requ1rements for Emergency Response Capab111ty (Gener1c Letter No. 82-33)," December 17, 1982.

2. Instrumentat1on for L1 ht-Water-Cooled Nuclear Power Plants to Assess Plant and Env1rons Cond1t1ons Dur1n and Fo low1n an Acc1dent, Regulatory Gu1de 1.97, Rev1s1on 2, NRC, Off1ce of Standards Development, December 1980.

3. Clar1f1cat1on of THI Act1on Plan Re u1rements Re u1rements for Emer enc Res onse Ca ab111t, NUREG-0737, Supplement No. l, NRC, Off1ce of Nuclear Reactor Regulat1on, January 1983.

4. Flor1da Power and L1ght Company letter, J. M. W1ll1ams, Jr. to 01rector, Off1ce of Nuclear Reactor Regulat1on, November 30, 1983.

5. Flor1da Power and L1ght Company letter, J. M. M1111ams, Jr. to 01rector, Off1ce of Nuclear Reactor Regulat1on, December 30, 1983.

6. Florida Power and L1ght Company letter, J. M. M1111ams, Jr. to Off1ce of Nuclear Reactor Regulat1on, NRC, "Conformance to Regulatory Gu1de 1.97,'ovember 18, 1985, L-85-417.

7. Instrumentat1on for L1 ht-Water-Cooled Nuclear Power'Plants to Assess Plant and Env1rons Cond1t1ons Dur1n and Follow1n an Acc1dent, Regulatory Gu1de l.97, Rev1s1on 3, NRC, Off1ce of Nuclear Regulatory Research, Hay l983.

8. Regulatory Gu1de 1.23 (Safety Gu1de 23), On-S1te Meteorolo 1cal

~Pro rams, RRC, February 17, 1972 or Proposed Revtssoo 1 to Regulatory Gu1de 1.23, Heteorolo 1cal Pro rams 1n Su ort of Nuclear Power Plants, NRC, Off1ce of Standards Development, September 1980.

18

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