ML20213H017

Conformance to Reg Guide 1.97 Sequoyah Nuclear Plant,Units 1 & 2

ML20213H017
Person / Time
Site:	Sequoyah
Issue date:	05/11/1987
From:	Udy A EG&G IDAHO, INC.
To:	NRC
Shared Package
ML20213G951	List: ML20213H017
References
CON-FIN-A-6483, RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 GL-82-33, NUDOCS 8705190101
Download: ML20213H017 (16)

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l' CONFORMANCE TO REGULATORY GUIDE 1.97 SEQUOYAH NUCLEAR PLANT, UNIT N05. 1 AND 2 g' .- .

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. EG&G Idaho, Inc.

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i Prepared for the

1. U.S. Nuclear Regulatory Commission Washington 0.C. 20555 Under DOE Centract No. OE-AC07-76IO01570 FIN No. A6483 i .

1 8705190101 B70511 DR ADOCK 0500 7 Issued: May 11, 1987

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CONFCRVANCE TO REGULAT0;v SU:0E 1.97 SEOUDYAH NUCLEAR PLANT. UNIT NC5. 1 MC 2

1. INTRODUCTICN On December 17, 1952, Generic Letter No. 82-33 (Reference 1) was issuec by D. G. Eisenhut, Director of tne Division of Licensing, Nuclear Reactor Regulatien, to all licensees of operating reactors, applicants for operating licenses and hoicers of construction permits. Inis letter inclucec additional clarification regarding Regulatory Guide 1.97, Revision 2 (Reference 2), relating to the requirements for emergency response capability. These requirements have been published as I

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Supplement I to NUREG-0737, "TMI Action Plan Requirements" (Reference 3).

The Tennessee Valley Authority, the licensee for the Sequoyah Nuclear Plant, provided a response to the generic letter on April 15, 1983 (Reference 4). The letter referred to a previous letter dated March 15, 1982 (Reference 5), for a review of the instrumentation provided for Regulatory Guide 1.97.

This interim report provides a'n evaluation of these submitta_ls.

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2. REVIEWREQUIREMENf5 Section 6.2 of NUREG-0737, Supplement 1, sets"forth the documentation

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f tobesubmittedinareporttotheNRCdescribingh,o~wthelicen$eemeets the guidance of Regulatory Guide 1.97 as applied to emergency response facilities. The submittal should include documentation that provices the following information for each variable snown in the applicatie tacie of Regulatory Guide 1.97.

1. Instrument range

2. Envi-cnmen al cualification i

3. Seismic cualification 4 Cuality assurance

5. Redundance and sensor location .

6. Power supply

7. Location of display

8. Schedule of installation or upgrade.

Further, the submittal should identify deviations ft:m the guidance in the Regulatory Guide and provide supporting justificatien or alternatives.

Subsequent to the issuance of the Generic letter, the NRC held regional meetings in February and March 1983 o answer licensee and applicant questions and concerns regarding the NRC policy on this matter.

At these meetings, it was noted that the NRC review would only address exceptions taken to the guidance of Regulatory Guide 1.97. Further, where licensees or applicants explicitly state that instrument systems conform or will conform to the ' provisions of ~ the guide it was _ roted that no 'further~

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staff review would be necessary., jherefore,[t[s'.7epo3t.only aUdresses

- exceptions- t'o 'theTuldance of' Regul'atory'Tuide :1!97. ~~ Th~e!following

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efaluatien i'~~an'au~it s d -of'the' licensee's submittals' based on the review policy described in~the NRC-regional meetingt.--~

3. EVALUATION The '.icensee provided a response to the N;C Ge*eric Letter 82-33 :.

Aprii '.5, 1983. This response referred to ar ear'4e submit:al of varch 15. 1952, which cescriced the licensee's :: sit'Or. on pcs:-accice ;

.onit:ed ; instrumer. ation. T-Js evaluatien 's :sse: On these su:m ::i s. 3

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3.1 Adnerence to Reculatory Guice 1.g7 The licensee stated inat all Type A, B anc C variables will est tne  ;

intent of Regulatory Guice 1.97 C'ategory 1 recuirements, and ina 'a ii Type D cnc E varia,bles will meet or exceed Category 3 requirements. A schecule for upgrading of instrumentation was proviced by the licensee.

Therefore, it is concluded that the licensee has provicec an explicit commitment on conformance to the guidance of Regulatory Guide 1.97 except for those exceptions that were justified as noted in Section 3.3.

3.2 Type A Variables o

.In that Regulatory Guide 1.97 does not specifically identify Type A variables, i.e. , those variables that provide information requirec f:r operator controlled safety actions, the licensee classif'ied the follcwing instrumentation channels as Type A variables, i 1. Neutron flux

2. Reactor coolant system (RCS) cold leg water temperature .

. . . _. .3 . RCS hot. leg water temperature

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4 RCS pressure _ ,

5. Degrees of subcooling

6. Containment sump water level

7. Containment area radiation E. Containment hycrogen concentration

9. Refueling ater s:cra;e tars level 3

.  : essuri:er level

• . ~ . . 5: ear gene-ater level .

12. Steamline pressure ,

13. Aexiliary feedwater flow 14 P-imary reactor containment pressure

15. High head injection pump running

16. Containment sump isolation valve position indicator

17. Secondary system radiation

18. Steam generator blowdown radiation

19. Main steamline radiation

20. Effluent radicactivity-noble gas ir condenser air exhaust.

Il of :ne above variables are also . included as. Type B, C. or D va[iables and meet Category 1 requirements consistent: with:tne'_requirementr'for-. _ .

__ Type A variables. -

3.3 Exceptions to Reculatory Guide 1.97 .

The licensee identified the following exceptions to the recuirements of Reg.' a:ery Guide 1. 97.

3 . 2 . ~. :ss';r. Cate :ry Excections e ':: wing ea ' ables are 'ce .-i fie: as Ca e;: y :y Re;.~ a:: y 3.':e . :- wnile tre '.icensee has 'urnisne: f rs: . e . a 'en fo - e:e

.a a: ' es ':n sa 's'y Catege y 3 recui e e-:s:

l. Residual heat removal (RHR) system flow (flow in low pressure injection system)

2. RHR heat excnanger outlet temperature

3. Containment sump water temperature 4 Accumulator tank level

5. Accumulator tank pressure

6. Accumulator isolation valve position ,

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7. Boric acid charging flow

8. Flow in high pressure injection system

9. Reactor coolant pump status

10. Primary system safety relief valve positions or flow through or pressure in relief valve lines Pressurizer heater status

11. _

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12; Main steam flow

13. Containment spray flow 14 Containment atmosphere temperature

15. Makeup flow-in

16. Letdown flow-out

~. 7 . Volume control tant :evel 5

IS. Component cooling water emoerature to engineerec safety feature (ESF) system

19. Componen: cooling water f1'ow to ESF system

20. Emergency ventilation damper position l l

21. Status of standby power and other energy sources important to safety

22. Condenser air removal system exhaust vent flow rate

23. Common plant vent flow rate r l

24. Containment sump water level-narrow range.

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The licensee indicates that these will meet or exceed Category 3 requirements, and that these variables are not needed for ensuring design basis behavior or for major contingency actions. The licensee indicates that these are not essential and therefore Category 3 is adequate.

l Regulatory Guide 1.97 is specific in defining a key variable as that single variable'"that most directly.ibdicates the acccmplishment of a

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safUy ~ function" or "the operaliorrof ar rafetPsystemi orT"rait'oa'~tI

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material release." For Types 0 and E variables, key variables are -

~ '" generally Category 2." The exception ~ ~of all ~the-aToie varfi5les f rom 1 Category 2 recommendations is not acceptable. The licensee should, on a case by case basis, identify the specific exceptions from t'he Category 2 recommendations and provice acequate justification for each exception.

3.3.2 Information to te Su:clied later Tne infcrmatice on the var'azies liste: below are eitre* 'centifie: ::.

the ' :ersee as : te su:: lie: la s*, or :ne 'r. formation :n :ne

~ ins: .rettat'en was si :ly miss'ng:

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1. Reactor coolant system (RCS) scluble beton concentratien (continuous sample)

2. Coolant level in reactor

3. Containmenteffluentradioactivity-noclegasesfromiderItified release points 4 Effluent racicactivity-noble gases from building or areas where penetrations and hatches are located

5. Condenser air removal system exhaust-neble gases and vent flow rate

6. Common plant vent-noble gases and vent flow rate

7. Particulates and halogens-all identified plant release points, sample

8. Post-accident sampling system.

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The licensee should provide the information Fequested in Generic ~~

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LetterNo.82-33,Sec.t_ ion _6.2_forth_e.sevari_ ables._fExceptions[~tothe reduiremeriis-tif-Regulatory-Guide ~-L47fshouldjbe-identif-ted2and 2

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3.3.3 RCS Hot and Cold Leo Water Temoerature The instrumentation for this variable has an upper limit of 700 F rather than 750 F as recc= mended by the Regulatory Guide. The licensee states in nis submittal that the maximum temperature during any expected transient is less than 700 F and that any temcerature above this would incicate inadecuate core cocling. We concur with the licensee that the succlied instrumentatien range is adequate and will provice the ir#crma-icn. Furtner, Revisien 3 of Re;;iatery Guice 1.97 lists tre .c:er limit recem encation at 700 ; nis is et ey tne licensee.

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_ J 2.3.4 :a:'a-ion Levei in Circu'a ine Primary Ccolan:

~t censee has not commi ;ed tc monitor this varia le, as instrum+ :1-ion was not availatie in early 1952. The licenses has sta":ec that as 'nstrumentation becomes available, it will be evalua:ec to de erm' e 'f installation is justified. We find that this ccomitment to evaluate newly deveicoed instrumentation for this variable and te sup;iy the prc:er instrumentation is acce:tacle. In the interim period, the licensee *til use the post-accident sampling system for this informat':n.

3.3.5 Cen:ainment Area Radiation The licensee has provided instrumentation for this variable with ranges :nat vary from the recommended range of 1 to 10 R/hr (type C) anc 7

107 R/hr (type E). The supplied range is 10 to 10 R/hr. While the upper 14 .it of the range is inclusive of the recommended range, the licensee nas not provided a justification for the deviation in the lower end of the range. The licensee has indicated that this instrumentatien will, when installed, meet the criteria for NUREG-0737, II.F.1 and NUREG-0578,2.1.8(b). These requirements do not specify a minimum rar.ge.

We finc :nis to be a. good faith attempt, as defined in NUREG-0737, Supplement.No.1-Section 3.7 (Reference .3), to meet NRC requirements anc ,

is , therefore,-acceptable.

However, the licensee should provide a schedule

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f.o.r. ins _tallation as required by Section 6.2(h) of Reference 3.

3.3.6 Centainment Hydrocen Concentration The licensee has provided instrumentation for this var'iable with a range of 0 to 10%. The recommended range is 0 to 30% for an ice condenser centaiament. Tne licensee has performed an analysis that shews ne w: st case hyc-: gen concentration will be less than 8% with the gicw plugs (nycroge- tgniters) c:erating. Thus, the inst-umentatien will be on 5: ate at any :a- icular time. The hydregen ignite-s' o era:icn is incica e:

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ne :cr -: rocm by :c-h incica se lights anc alar s (Ty e C, Categ: y 3, n:: re:.- ec by Regu atory Guide 1.97).

l Accit'onally, tne censee's

!:-a::':ert sam:li .g system car. ;r0 vide c've-se incica;':- fcr tn's war a 'E. We concue with the lice-see ina tre ra ge Orevicec is ace:.a e.

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3.3.7 RHR Hea: 5xchancer Outle: Temoe-a:ure The licensee has proviced instrumentation for this variable with a The'up;er range of 50 :: 400 F rather than the recommencec 22 to 350 F.

limit of tne recommendec range is inclucec in the supplied range. The licensee has not provided a justification for the deviation of the minimum range. Revision 3 of Regulatory Guide 1.97 (Revision 6) ircreases the rinimum recommenced range to 40 F. The range supp'ied by the licensee coes not satisfy nis either. The licensee snoulc provide justification that shows the minimum range -of 50 F is adecuate.

3.3.8 Accumulator Tank Level and Pressure The licensee has supplied instrumentation for these variables with a range for level of the top 20 in. and for pressure, O to 700 psig rather than the recommended 10 to 90% volume (level) and 0 to 750 psig (pressure).

The licensee indicates that the range for level is restricted to the top twenty inches so they can meet the accuracy requirements imposed by technical specifications. Since the range of the instrumentation was not related to the accumulator volume, a judgement cannot be made that the

_ range provided is adecuate to monitor the operation of the accumulators

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of this' instrumentation is adequate to monitor the operation of the

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~ accumulators, or that such information can be derived by diverse instrumentation.

The accumulator pressure is maintained between 385.and 447 psis. This is within the range suoplied. Thus, the range is an acceptable deviation because it adecuately covers the expected range of accumulator pressure.

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3.3.9' Eoric Acid Charcine .:1:a The licensee has sucoliec '*str; enta.icn for tnis varia:ie a'th a range of'O to 100% flow, rather nan the recommencec 0 :: 110% flew. The licensee provided no justification for this deviation. The licensee shoul:

provide justification for this deviation.

3.3.10 p-essuri:er Heater Status Regula: cry Guide 1.97 reccmmends monitorinc the electric current for the pressurizer heaters. The licensee has suoplied a status (heater on) lignt for each pressurizer heater group. The licensee,has provided no justification for this deviation. Circuit breaker position indicates the

esition of the circuit breaker, but coes not i ndicate open or partially shorted heater elements. Instrumentation is available which would allow

, the current to be monitored. The licensee shoulc provide justification fer o this deviation from the recem endatiens of Regulatory Guide 1.97.

3.3.11 Quench Tank Temperature The licensee has supplied instrumentation for this variable with.a _ _ . _ _ . _ _ _ . .

rarge of 50 to 300 F rather than the recemmenced 50 to 750 F. The licenses has proviced no justification for this deviation. The licensee should - -

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provide justification 'that th~e ran~gi-(50;300*F) Ts ~adiobate'"

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- . . -3.3.12 Steam Generator level.

-The licensee has suopliec one Category 3 wice range and three Category I narrow range instrument cnannels for this variable. The Regulatory Guide re :mmends recundant Category I wice range enannels. The

~ ;ur:0se as stated in the reg;1 ate *y ;uice. is te .eni:cr operation of the staar ge* erat:r in a pos -a::' e": ::":'t':*. Te arr:w *ange i.strune*u

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J 3.3.12 Steam Generator Pressure The it:ensee has su: plied instrumer. ation for this varia:le a;it a range of 0 : 1200 psig. The range recommended by Regula: cry Guice 1.97 is atmospneric :: 2C% above 1064 psig, tne icwest safety valve setting, or 1277 psig. The licensee justifies this deviation by stating that it is small. Tne suppliec range is 7.4% higher than the highes safety valve setting (1117 psig). The licensee should provide additional justification for the exis-ing range.

3.3.14 Condensate Storace Tank Water Level

.The licensee has provided Category 3 instrumentation for this variacle. Category 1 instrumentation is recommended by Regulatory Guide 1.97. The licensee justifies this deviation by pointing out that the safety grade essential raw ccoling water system automatically backs up the condensate storage tank as a water source for the auxiliary feecwater j- system. The auxiliary feecwater system is the only post-accident system that uses the condensate storage tank as a water, source. Therefore, we conclude that the justification proviced by the licensee for this deviation is acceptable.

3 3.15_._-Heat Removal by the Containment Fan Heat Removal System -

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" "" - The' licensee has not proviced this instrumentation, since the far.s are . . - - . --

isolated on a containment Phase B isolation signal. Thus, in the

=cs:-accident situation, this system is no operating and, therefore, will not provide heat removal. The justification providec by the licensee for not supplying instrumentation for this variable is considered acceptacle.

3.3.16 Comocnent Coelant Water (CCW) Teneerature to ESF Systems Reguia:Ory Gd ce 1.97 ret:mmends instrumen ation for :nis varia:'e a i: a range f 32 te 200*F m:nitor tre ::e-at'en Of e C"W syste-

e 'i:Ersee nas su00lieC ins rumentati:P. 0r t*is v!"iacIe with a rirse via sa; ex nar.gers a*c tr.e l

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Tre CCW is C00'.ec Oy rive aa e 11

se vice water system. The licensee indicates :na: there is nc tecnr.ical tasis for increasing tne present range. We 'in: the justification fcr :nis

-arge una::eptable. The licenses snould previce accitional justificati:n for :ne existing range.

3.3.17 Waste Gas Decay Tank (Gas Holduo Tank) Oressure Ine licensee has supplied instrumentation for this variable with a range of 0 tc 150 psig. This is the vessel cesign pressure. The Regulatory Guice recommends a range to 150% of cesign pressure. The licensee indicates that relief valves prevent the pressure in the tank from exceeding the design pressure. Thus, the tank pressure should not exceed the design pressure by action of the pressure relief valves. The licensee indicates that having a range in excess of this pressure serves no purpose. Based on the pressure relief valves operating to prevent a pressure in excess of the instrument range, we concur that this deviation is acceptable.

3.3.18 Status of Standby Power and Other Enercy Sources Imcortant to Safety i l

The licensee has provided instrumentation for these variables that, 1 -

-l L , T except for the recommended category (see Section ~3:3.1) anif thi 4.16_.kV--- ~~ ~ ~ ~ - ~ ~. !

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-- - ~ Class IE buses, meets the recommenda'tioni of Regulatorf-~ Guide ~E97.

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licenset has not provided justification for not monitoring the status- of __-__-- -- --

- ~ the 4.16 kV Class 1E buses. The

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licensee should justify the lack of instrumentation for these buses.

3.3.19 Plant and Environs Radiation (Portable Instrumentation)

The licensee has provided instrumentatien for this variable with ra.ces : a; are inclusive of recommencations Of 'eguia:Ory Guide 1.97 er:e:: for S/T whic7 shoulc have a range up 0 '0 racs/hr. SL:Diied

-ta'e 'ns *umentatien for this varia

le cas a arge un tc 100 R/nr. T .e 1 :ensee :ic rc: p 0vice justification fcr : 's :ev'a-icr in range 12

s' recui ements; however, we find tnat tnis deviation is acceptable, as tne ins: umentation is portatie anc would not be used to assess levels of radiat'on greater than :ne range provided ty the li:er.see.

4 CONCLUSIONS ,

Basec on our review we find that the licensee either conforms to or is justified in deviating from the guidance of Regulatory Guide 1.97 with the following exceptions:

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1. There are 24 variables which should be discussed and deviations from Category 2 requirements justified individually (see Section 3.3.1).

2. There are 8 variables for which the information requested by Generic Letter 82-33 should be provided (see Section 3.3.2).

3. RHR heat exchanger outlet temperature--the licensee should provide justification for a deviation in the minimum range (see Section 3.3.7).

4 Accumulator tank leve_l _-The_ licensee has not justified that the twenty inch-range is adequate. This deviation should be

_ _ . g fgd~ W y icEKsee-(see"Section 3.3.8).

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5. Boric acid 'c'harging flow--TEis'~ instrumentation does not have a range as recommenced in the regulatory guide. This deviation should be justified by the licensee (see Section 3.3.9).

6. Pressurizer heater status--This instrumentation is for a different parameter than recommendec by the regulatory guide.

The licensee should provice justification for the use of an alternate variable (see Section 3.3.10). l

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7. Quencn tank temperature--This instrumentation does net have a range as recommenced in the regulatory guide. This ceviation should be justified by the licensee (see Section 3.3.11).

8. Steam generator level--The licensee does not have recundant ,

Category 1, wide range channels for this variable. This deviation should be justified by the licensee (see Section 3.3.12).

9. Steam generator pressure--the licensee should provide j justification for the deviation from the range recommendations (see Section 3.3.13).

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10. Component cooling water temperature to ESF systems--the licensee should provide additional justification for the preposed deviation (see Section 3.3.16).

11. Status of standby power--the licensee should justify not monitoring the status of the 4.16 kV Class IE buses (see Section 3.3.18).

5. REFERENCES

'1:-kRE-letter, D. G. Eisenhut to all Licensees of Operating Reactors, - - - - -- -

Applicants for Operating Licenses, and Holders of Construction " ~~~

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Permits, " Supplement No. I to NUREG-0737--Requirements for Emergency - - - - -

Resp ~cnle Capab'ility (Ge'neric Letter No. 82-33)," December 17~,~ 1982.

2. Instrumentatien for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Concitions Ouring and Fo11 ewing an Accicent, Regulatory Guide 1.97, Revision 2, U.S. Nuclear Regulatory C0mmission (NRC), Office of Standards Development, December 1980.

3. Clarification of TMI Action Plan Recuirements. Recuirements fer Emercer.cy Rescense Cacao 111ty, NUREG-0737 Supplement No.1, NRC, Cf fice cf Nucisar Reactor Regulation, January 1953.

4 ~e >nessee Valley Authcri t y (TVA) letter, L. M. Mills :: Cire tcr ;f Nuclea- 9eacter Regulatice, NRC, A;M' 13. '933. 00:ket Ncs. 5^-327 arc E0-328.

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NRC, Marcn 15, 1932, Dccket Nes, 50-327 inc 5 -323.

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. Psi a-Regulatory Guice 1.97, Revision 3, NF. , Office of Nclear Regulatcry Researcn, May . : -,ca. .

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