ML19323B909

Forwards Response to NRC Questions Re Facility Special Tests,Test Instructions,Description of Operating Training Provided by Special Test Program & Miscellaneous Procedures

ML19323B909
Person / Time
Site:	Sequoyah
Issue date:	05/12/1980
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	Rubenstein L Office of Nuclear Reactor Regulation
Shared Package
ML19323B910	List: ML19323B909 ML19323B915 ML19323B919 ML19323B927 ML19323B930 ML19323B932 ML19323B934 ML19323B937 ML19323B944 ML19323B945 ML19323B950
References
NUDOCS 8005140410
Download: ML19323B909 (11)

Text

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e b 400 Chestnut Street Tower II 80051 48 May 12, 1980 Director of Nuclear Reactor Regulation Attention: Mr. L. S. Rubenstein, Acting Chief .

Light Water Reactors Branch No. 4 Division of Project Management U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear ik. Rubenstein:

In the Matter of the Application of ) Docket No. 50-327 Tennessee Valley Authority )

Enclosed for use in your review of the Sequoyah Nuclear Plant unit 1 special low-power test program is the following information.

i 1. Three copies of the special test instructions, section 5 of the Master Plan for the Special Low-Power Test Program, which have been reviewed by the Plant Operations Review Comnittee and approved for use by the plant superintendent. These procedures supersede all other revisions. Ten additional copies will be provided under separate cover for use in revision of your copies of the >bster Plan.

2. Ten copies of the responses to the questions on the special test program transmitted to TVA in your letter to H. G. Parris dated April 10, 1980. I

3. Ten copies of a description of operator training provided by the sdl special test program.

If you have any questions, please get in touch with M. J. Burzynski at FTS 854-2581.

Very truly yours, TENNESSEE VALLEY AUTHORITY l l

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M_ G, L. M. Mills, Manager Nuclear Regulation and Safety Enclosures

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THIS DOCUMENT CONTAINS P00R QUAulnf PAGES

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. ENCLOSURE 2 RESPONSE TO MRC QUESTIONS ON SEQUOYAll SPECIAL TESTS RECEIVED JAKUARY 24, 1980 1.0 a) The special tests are scheduled as a part of the nouaal startup test program. The sequence in which the individual tests are performed is a part of the master sequencing instruction (S-U 7.1) in the Sec,uoyah Startup Procedurcs. A copy of this instruction is included in the Master Plan For the Special Test Program which has been provided for your staff review.

b) Each individual test specifics the conditions to be established and naintained. Manual operator actions are provided if certain limits are e::cceded. All cmcrgency procedures are applicable.

Depending on the circumstances of the emergency, the appropriate emergency procedure will be used.

c) At the conclusien of each test there are specific steps, with signoffs, to reinstate all equipment to normal unless another test uhich requires the same alignment is to immediately follow, d) TVA has issued an administrative procedure (Scquoyah Nuclear Plant, Standard Practice SQA 109) which adcresses the ccnduct of the special test program. This procedure includes the follouing information for the Special Test Program; purpose and objective, responsibility of organizations, preparation, review and approval of instructions, conduct of tests (including other applicable administrative procedures), and evaluation and .oproval of results.

This procedure also specifies that the shift engineer (SRO),

assisted by the assistant si.e.ft engineer (SRO) and licensed unit operators, is responsibic fc. 4-'stituting immediate action in any situation to clininate diffis es and to preclude violation of the operating license, technica. specifications, or to avert possible injury to personnel or equipment damage.

The test engineer can stop a test when, in his opinion, conditions warrant such action. Ilouever, he has no authority over the

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licensed operator. If the test engineer stops a test, it is,the licensed operator'c responsibility to put the plant in an accept-able condition.

2. a) Any special arrangements of the plant outside normal operating procedures arc outlined in the prerequisites of each test.

b) The main control board has two trend recorders each of which having two recording pens. These recorders are used by operators

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2 pISPO :SE TO !.'RC QUESTIONS ON SEQUOYAH SPECIAL TESTS RECElVED JA';P/2Y 24,1980 to trend parameter of the most interest during a particular

, operation. At this time three of the recorders vill be used to trend core exit thermocouples with the fourth permanently recording the reactor coolant saturation margin. The rest of thu thermocouples are recorded at five minute intervals j by the computer and printed on the trend printer.

c) The reactor coolant bypass flow fraction will change under i

natural circulation; however, the calorimetrics run to deter-mine core power are done under forced flow conditions with all j four RCP's running.

{ d) Normal operations precedures are used throughout the special test program. Those necessary deviations are contained in the special test instruction. These test procedures have been revicued relative to the normal operating procedures to eliminate possible ambiguitics. .

e) Special Test 7 is the only test in which all auxiliary %uilding li;;hting is shut off. This was the only reason for evacuating

personnel.  !

f) In steps requiring the movcment of valves or equipment which i

might cause confusion for the operator (as in step 5.10), the procedures have been changed to include multiple signoffs. It has not becu the policy in these or the startup tests to specity

or require individual signoffs for every valve movement, g) The procedures have been reviewed in light of this comment and

! changes incorporated where applicable.

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3. a) There are no plans to run the diesels just prior to this test.

The Surveillance Instructions regarding the diesel generators are performed periodically as required by the ST!:. This S.I. uill not be run just prior to the conduct of test 7.

.b) (1) The operator is m arc of the direction of change of charging and steam flou to increase the saturation margin through both l normal training and simulator training on these tests.'

!. (2) The results of all the tests vill be evaluated for possible i

corrections. or improvements to plant operating instructions.

l c) (1) As presently scheduled there is little or no~ time between

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the' tests. If a significant delay is expected between tests,

the provision to return all safety features to normal is in

. cach test.

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RESPO::SE TO ?:nC QUESTIO::S ON SEQUOYAll SPECLiL TESTS RECEIVED Jida!!AY 24, 1980 (2) The whole data sheet is referenced to be carried out at the intervals indicated in each page. These pages have clearly established intervals betre,en data accumulation. Ti.e page concerning the batteries is no more importmt than the other pages, d) (1) 7ter.s 2.6 and 2.7 have been deleted from the procedure. The Westinghouse safety evaluation and the table of Technical Specification Exceptions clearly define which trips are inoperable. The only safety feature being modified in any test is the nutomatic initiation of Safety Injection.

(2) Reactor poner and intermediate range channels and the reactivity computer will be monitored continuously. The five minute intervals indicated in the test are recording intervals to be used on the plant computer for trend printing these parameters. This printed trend is to be used as a permanent copy of the paraueters. ,

(3) As indicated in the reply to question 2.6., one of c.._ nur trend recorders pennanently monitors saturation margin. The tests have been corrected to reflect this.

(4) See reply to question 1.c.

c) This was a typcgraphical error and has since been afded to t..

procedure.

4. a & b) The establishment and maintenance of natural circulaticn for two-phase and single-phase flou conditions require essentially the same operator actions. These actions vould be the same as long as adequate core cooling is deconstrated by the establish-ment of the conditions indicated in these tests and the pro-cedures for natural circulation. In the event those conditions are not met and adcquate core cooling is not demonstrated, the operator would take action as defined by the emergency pre-cedures for inadequate core cooling. Training in the use of these procedures is provided on the Sequoyah Simulator.

5. The safety analysis has been submitted.

6. This data is being accumulated in the existing preoperational test Ul.8, RCS Flou Coastdown. If you wish to review this procedure, we vill provide it to you.

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4 RESPO:;SC TO ERC QUESTIONS 0:: SEQUOYAH SPECIAL TESTS RECEIVED JA:rARY 24, 1980

7. It is not the purpose of any of these tects to quantitatively identify system heat losses. The tests are rather to identify, given the various heat locces, deprecsuiraation and cooldown rates under certaia conditions and give the operator enper*cnce with system response in these conditions.

3. Under natural circulation conditions, turbulent flow will enist in the reactor coolant system piping. With these flow conditions uc do not expect the indicated temperature readings to be lower than the actual bulk coolant temperature. In addition, the core exit thermo-couples are monitored as an indication of natural circulation conditiens and caturation margin.

i 9. An estimate of the radiation levels existing at the completion of the Jou power test program is very difficult due to the uncertainty in crud disposition. Houcver, TVA has examined the impicmentation requirements stemming f rom the NRR Lessons Learned Task Force Kemeny Ccomission, and the Tack Action Plan, and concludes that implemen-tation of these requirements will not be precluded by this low pouer operation.

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ENCLOSURE 3 OPERATI;;G EXp".n".EUCE PROVIDZD DY TliE SPECIAL TEST PROGRAM The follovlun is a description of the operating c::perience provided by the special test ircrram. It discusses the scheduling frequency and duration expected to accomplish the desired training objectives for each test. These objectives will be evaluated as the pror, ram progresses and; changes will be made accordingly.

The nchedule is arranr,cd to start each shift with the basic Natural Circula-tion Test (Test 1) and progress to a more complicated test. Each operating shift is required to tign off on each test as shcwn in the attached Table 7 from the startup test sequencing document (S.U. 7.1).

Test 1: The natural Circula. ion Test should be run at lease once and if time permits twice per shift. Only one group will perform the test en an eight ho:r shift. In this way each operator can par- 4 ticipate in both en :ry into and exit from Natural Circulation and observe transient at.d steady state unit behavior.

Euen grcup should perform this test before performing any other natural circulation test.

Tect 9A: The Forced Circulation Cooldown Test is not designed to provide operator training, rather it gathers data for the Baron Mi::ing and Cooldown Test. Eccause of this objective, the test will be performed once. Since this is not a natural circulatien test, the groups performing the test need not have performed Test 1.

Test 9B: Each operator group should have performed Test 1 before performing this test. This test uill be performed tuice. First, the schedule calls for three groups to cover two shifts. It is suggested the 1st shift start the natural circulation cooldown and cool down appre::inately 30 F. The float group should come in approximately four heues early to perform an additional 40 F cooldcun uhile the

- day shift cools down the reunining 30 F. In this way all three shifts perform a natural circulation cooldown and will be exposed to the unit and instrument transient behavior. Next, the schedule calls for tuo groups to cover two shifts. The test should be started halfway through the shift, cooldown 70 F then turned over to the oncoming shift for the remaining 300F.

Ilue heat up portion of the test is intended to obtain additional data and provides no designed operator training function.

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Test 8: The Establishment of Natural Circulation From Stagnant Conditions Test should be run at least once and if time permits twice per shift. Only one group _ will perform the test on an eight hour t

shift with the exception of the float group. They should_per-

, form the test following the test completion by the day shift.

, The float group may overlap _into the evening shift to complete i the test. In this way each group will be exposed to the problems j associated with and the expected paraceter responses associated wl:P the initiation of natural circulation from a stagnant flow j cond'. tion.

} Test 3 5 5: Natural Circulation with Loss of Pressurizer Heaters Test and

Natural Circulation at Reduced Pressure Test'will be performed' l simultaneously. As a training tool, Special Test 3 will give the operators experience in controlling the saturation margin l during depressurization using charging flow and S/C steam flow.

1 Special Test 5 is actually a continuation of ST3 as far as a l training expericnce is concerned. The same techniques for saturation margin control are used at the-lower pressu.res.

J. If subcoolian in thc . pressurizer occurs, further experience

! will be gained because of the increased sensitivity of the RCS l pressure to charging and letdown flow. In order for cach j operator to participate to the maximum extent possible, the two 4

tests should be run together by only one group during an cicht hour shift. An exception is that the float group will be brought in halfway through first shift to first observe and then ncar.the 4

end of the shift operate the CVCS. If necessary, they.will con-tinue through the second shif t in order to meet the desired 1 training objectives..

Test 4: Effect of Steam Concrator Secondary Side Isolation on Natural

. Circulation Test will be performed in its entirity only once.

! The test duration will cover approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. .The third l- shift will enter natrual circulation then first remove one steam j generator and then another from service. The two S/G will be j returned to service but natural circulation maintained. The off l-group will . overlap and repent _ the isolation-recovery process.

This action will continue until each group isolates and l , unisolates two stean generators. Eccause of the number of items to be observed and: the off normal system responses cach group should perform all steps from 5.3 to 5.17.

Test 2: Untural Circulation with Simulated Loss of Offsite AC Power Test ,

! should be run as fow times as possible because of the possibility l'

of equipment damage, but still allowing all operations groups;to observe and/or take part in the test. ' Actual system opera'tions

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!' will be performed by the -group ' responsible'. for shif t coverage.

. Observer. personnel'will only observe. Eccause of-the nature of e mm. , , m rg <~~ n v +,~me.- w . nvq 4 g - pe e v

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Test 2: this test, the training objective can be met as an observer. This (Cont.) is true since the major steps are verification of ucte autcmatic action. The major portion of the recovery is covered in an Emergency Operating Instruction and is practiced at the Training Center. The schcdule calls for the test to be performed three tines, two of which will have an observer group assigned to follow the test.

Test 7: Sinulated loss of All Onsite and Offsite AC Power Test will be initiated only once. Because of the operational experience that can be gained 1,y locally controlling the S/G, PORVS and the auxiliary fecaunter system, every operations group should per-form the lo.cl control function. The test will Le initiated late on the evening shift and continue until all groups have participated. Following test initiation the on-shift operation group uill obtain lecal control and maintain Wat Standby condition.

Af ter this inicial performance, the 125-volt vital battery can be unloaded. As each new operations group prepares to take control the S/G PCdV3 and auniliary f ecduater systeni, the systens will be returned to the pre-recovery co,ndition. In this way each operator will take manual control, adjust to the desired flow rate, and maintain the Steam Generator level and RCS temperature at the norrel !!ot Standby valves.

Test 6: Cooldcun Capability of the Charging and Letdown Test vill be performed by each operations group whenever the opportunity arises. The reactor is subcritical and the primary systen is in hot standby.

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':cccial Test /

Te s t ' arc Shif: Perforranc2 E:Te r te d Gcneral Corrents Euratica (hr) 3 Establish SC from Groupt

_ /__ __ _ 8 Specici Test S shculd be : t.n Stagnr.nt Conditions Group 2 ' d - - - -t t:f r c . All five 2, crc:icn-Grcup3 ,

3  ;:r:r.c s r s t pcr:::iretc it the Group 4 .. 3 s :;.n:- a t star: :::nsient.

Grcup5 / 8 (Tast Di r[cto r) e 3  !!atural Circulation GroupI / 20th Test Special Test #2 cnd 45 should

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w "i th l es of . Group 1 / -_ La rc.fer.ad siruit:niously.

Fressurizer Heaters Group 3 / The test dirac:rr est assi:n Groupa / 3 rub dire.ctors esch responsible Group 5 _' S for a test. The ter: directer (Tect Dircctcr) 8 is respcasible for cocrdinati.

the test.

5 ';aturhl Circulation at Feduced Pressurc Groupl_ / 3 Group 2 / 8 Groupi-.

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Group 5 /

(Tent Director) 4 Steam Generater Group 1 / Special Test f 4 c.hould be run Isolation in NC*- Group 2 / 12 t ei 7_ '11 fivc CT erations Group 3 / 12 Groups r.v:t participate to the Grounif

/ extent t:,a en ch rerforr.; a Gro up 5 / stese. generater isolation :nJ

('I e a t Di re c to r) reestablishren: of n.3: ural cir-culatien iclic.cing the raturn ci the 5/O to service.

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TABLE 7 SFOUENCE OF STT.75 FOR ':ATUIAI CIRCUATIO?I TEST 1':G .

f.rE. This sequence can be aedified b: the tcs: director.

Special Test f Test.::ame Shift Pe r fo rnr.nce Expected Cencral Co: ents Duration (hr) .

2 .  !:atural Circulatien Crcup 1 / ipecial Test f 2 should be run

!!ith Simulated Loss

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Grot.p 2 / 12 three tiras & ST "7 shculd be of Of fsite AC Power Group 3 / 12 run ence. All five 0; cr:tions Group 4 '

3 Croips rust pcrticipate to the Group 5 /_ _ extent that each ebserves thi-(Test Director) unit resper.se epon test initiatica

.ind parier.a scr2 pertica of the 7 Sim: lated Loss of Group 1 /

.stahi:atica and recevery operaticr..

All Casite and Group 2 / S T i' 7

.i. Offsite t.C Power Creup 3 / 12  ?!0TE: Af ter cach shif t rcrforr.s v

ni Group I. / the requirad stabilizatica Group 5 / __ __ functicn in enual return (Test Director) the ce:; cr.cnt to auto the::

back to r.anual. In this va;.

each crcu establishes n.- -

us1 centrol.

6 Cecidewn Capability Group 1 / 4 Special Test M can b2 conducted if the Charging and Group 2 / 4 at varicus tires throur.h but the letdown Crcup 3 / .

4 speci31 test schedu.e in vhich Group 4 / -

4 hat t,r.utd: n cer.di: f ons exist.

Group 5 _/ 4 all fiv2 crerating groups should complete the tact p rio r to con-cluding special test s che diile.

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