ML19291A638

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Summary of 790425 Meeting w/C-E Re Natural Circulation Capabilities
ML19291A638
Person / Time
Issue date: 05/02/1979
From: Thadani A
Office of Nuclear Reactor Regulation
To: Ross D
Office of Nuclear Reactor Regulation
References
NUDOCS 7905240476
Download: ML19291A638 (40)
v • d • e


Text

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g WASHINGTON. D. C. 20553 t: Y.~...E./ MY 2 1979 MEMORANDUM FOR: D. F. Ross, Jr., Deputy Director, DpM FROM: A. C. Thadani, Reactor Systems Branch, DSS

SUBJECT:

SUMMARY

OF MEETING ON NATURAL CIRCULATION WITH COMBUSTION ENGINEERING ON APRIL 25, 1979 Ashok Thadarii opened the meeting witn a statement of the objectives: 1. Discuss the natural circulation capability for CE plants. 2. Discuss current instructions available to the operator regarding natural circulation - when to initiate, when not to initiate, and the potential consequences. 3. Discuss other items such as NRC Bulletin 53, and Michelson Report. Ray Mills (CE) stated that CE intended to discuss the design of the CE plants with respect to natural circulation (agenda enclosed). They were not prepared to discuss additional iters, but would do the best they could with the people available. Dick Daleas of CE bcgan by describing the CE reactor coolant system design. Key points of his discussion were as follows (copies of slides attached - dots are analytical, solid lines are test data). 1. The CE system arrangement (elevation, etc.) is generic for all plants (raised loops). 2. The surge line for the pressuri::er is located entirely above the hot leg piping. 3. He described the analytical capability to predict natural circulation performance. a. Assume reactor coolant pumps bind at 5"o of full flow after coastdown. b. Assume variable reactor coolant pumo resistance (with ficw) based on vendor data. In natural circulation the pumps crovide apcroxi-mately 75'; of icop resistance. The model used is an inhouse ccde (Li') which will only run c. for subcooled conditions, d. Steam generator is modeled with 1 nede.

Contact:

Ashok Thadani, NRR 492-7341 7905240 THIS DOCUMENT CONTAINS g POOR QUAUTY PAGES

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CE Power Ascension Test Program - a. All operating CE plants have conducted a natural circulation test. The tests were conducted from approximately 35%-40% pcwer by opening the reactor coolant pump breakers. The reactor trips on Icw reactor coolant flow. The operator manually restores steam generator levels (very slowly) with auxiliary feedwater. Steam generators boil down for 1 to 2 hours at which time Test B is then completed. The staff incuired as to what kind of cooling rates could be achieved due to rapid feeding by the operator. CE said that it was possible that overccoling could be severe enough to lose pressurizer level, but that this would not happen since 1) proce-dures contained precautionary statements and the operators had a " good feel" for manual water level control with the auxiliary feedwater systems in CE plants. b. The staff also asked how long the plant could go with all feedwater lost? CE stated that they would have to evaluate. They did say that for a loss of offsite power, the plant enters natural circu-lation automatically but that to maintain natural circulation, manual action by the operator to control steam generator level is necessary at approximately twenty minutes. 5. CE described the test data frem 1 power ascension test and compared the results to the predicted values. a. In general, the data agreed quite well with the predicted results. Differences did exist due to test conditions being different from analytical assumptions - such as manual control of pressure by the operator using pressurizer heaters. An interesting parameter difference is the flow to power ratio s20 minutes when the operator secured AFJ. CE attributes this ancrr.aly to the 1 node steam generator model which would not correctly credict the swell that occurred in the stear generator when AFJ was secured. The swell would raise the thermal center in the steam generator and increase reactor coolant flow, rather than decrease it as predicted. b. Cne phenomenon occurred for all natural circulation tests. Hot leg temperature initially decreases after reactor trip and then slowly increases to a point less than the initial value as natural circulation is established. The AT's for natural circulation are always less thar, the AT's at pcwer. This is indicated by the flow to pcwer ratio always being greater than 1. 5. CE described the field data available as a result of actual natural circulation occurrences on operating plants. a. Palisades ecarated from grid and maintained hot standby and natural circulation for approximately 5 nours. b. St. Lucie - loss of instrument air resulted in reactor coolant

D. F. Ross, Jr. MAY 0 S 73 pumo seal failure. Unit cooled down on natural circulation and went on shutdown cooling in approximately 10 hours. c. St. Lucie - separated from grid and maintained hot standby and natural circulation for approximately 4 hours. 7. An analysis of a loss of forced circulation while operating at hot standby with one reactor coolant pump running was reviewed. With one reactor coolant pump running in one loop, reverse flow is occurring in the ocposite loop as well as the other cold leg in the same loop. The analysis shows that after the pump is tripped, natural circulation occurred and a stable plant condition achieved, even from a reverse flow condition. 8. CE discussed the pressure control capability of the pressurizer after a loss of pressurizer heaters. A CE analysis assuming no pressurizer heaters, plots pressurizer pressure as a function of system leakage. Heat losses of the pressurizer are based on field data (see slide). Generally several hours are available before appreciable pressure losses to the environment would occur. The staff identified several additional areas of interest that related to natural circulation. The following is a summary of these areas and the CE response. a. Pressurizer Heaters - Not normally powered from a vital bus. b. Reactor Trip - Turbine Trip - All CE plants have a direct reactor trip from a turbine trip. c. Pilot Operated Relief Valve - On CE plants (operating) the PORV open set point is the same as the high pressure reactor trip set point. To the best of their knowledge, CE does not know of any challenge to a PORV on their operating plants, howover, they requested more time to check. They also know of no reports of PORVs failing to close af ter ocening on CE plants. They will confirm this. d. Control Room - Procedures for impending saturation conditions - CE is not sure what procedures are currently available. A representative from BG&E was asked but also did not know. The staff requested this information from BGE & CE. Jim Crawford of CE presented the current guidelines provided to the customers by CE and also their thoughts on what improvements could be made along these lines (see slides). Key points to these discussions are as follows:

D. F. Ross, Jr. MAY 2 ST3 a. CE and the staff both noted that additional work was necessary on remedies to unanticipated plant conditions, if observed by the operator. For example, a procedure would say: " Verify reactor trip", but will not say what to do if reactor trip has not occurred. The same is true of natural circulation related parameters. b. The information in the CE presentation on new procedures was preliminary, however wnen asked about their implementation schedule, said that they thought that guidance would be provided to their customers within one month, c. CE is considering giving guidance to the operating plants to maintain two reactor coolant pumps running if power is available even if reactor coolant pressure decreases to saturation. d. The staff noted that many of the parameter values such as margin to subcooling needed a basis and further consideration. CE stated that their criteria were preliminary and agreed to address these areas. e. The staff noted that an additional remedy to loss of natural circulation should be to attempt to restore forced flow. f. The staff requested that CE provide their analysis of how much gas could come out of solution assuming normal concentration and its effect on natural circulation. g. The staff requested all indications that operator will have of PORV positicn. Ray Mills of CE discussed the CE simulation capability of natural circulation on their simulator. The simulator does not currently simulate natural circulation. CE has started an investigation of program modification to achieve this capability. Ashok Thadani of the staff reviewed the staff agenda (attached) with CE, noting that all staff concerns had not yet been responded to. It was agreed that NRC staff would call CE on April 25, 1979 to discuss the need for additional information. Ashok C. Thadani Reactor Systems Branch Division of Systems Safety

Enclosures:

1. Meeting Surrary 2. Slides

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TYPICAL LOOP MATURAL CIRCULATION CAPABILITY CORE HEAT Flow Flow-To-power (%) (I) RATIO SOURCE 0.5 2.5 4 TEST / ANALYSIS 2 3.8 1.9 ANALYSIS 4 4.8 1.2 ANALYSIS TYPICAL LOOP FLOW FOLLOWillG RCP C0ASTDOUN TIME CORE HEAT Flow Flo.v-To-PowtR (SEC) (%) (%) RATIO SoVRCE 60 4 15 3.75 TEST / ANALYSIS 100 3.5 10 2.9 TEST / ANALYSIS CoNCLUSIcN: FoLLoWING RCP CoASTDoWN FRoM POWER OPERATicN Do floT EXPECT LooPSI ANY GREATER THAN INITIAL VALUE.

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SUMMARY

1. HATURAL CIRCULATIO.'t IS VERIFIED IN EVERY C-E PLANT. 2. NATURAL CIRCULATION C00LDORI CAPABILITY OF C-E PLMIT HAS BEEN VERIFIED. 3. ETHODS OF ANALYSIS HAVE BEEN VERIFIED. 4. SEVERAL INDICAT101S OF ADEQUATE NATURAL CIRCULATION ARE AVAILABLE IN THE PLANT.

NATURAL CIRCULATION GUIDELINES VERIFY REACTOR TRIP ATTEMPT TO START DIESEL GENERATORS VERIFY CORE THERMAL CIRCULATION FLO'4 - TYPICAL.iT PO'JER VALUES ARE GIVEN VERIFY STEAM DUMP AT SET POINT - TAKE MANUAL CONTROL IF AIR SYSTEM IS LOST START STEA'4 DRIVEN AUXILIARY FEEDWATER PD9 AND RESTORE STEAM GENERATOR WATER LEVEL MINIMIZE REDUCTION OF REACTOR CCOLA'iT VOLDIE 3Y MIND!IZING C00LDOWN. DO NOT OVERFEED STEAM GENERATOR OR DDIP EXCESSIVE STEAM PRIMA 3.Y PRESSURE WILL DROP IF HEATERS ARE NOT ENERGIZED. MAINTAIN 200 PSI PRESSURE MARGIN. DD9 STEA'4 TO CONTROL T HOT o .us :

nn.

, c.. = v. g r v.4 :_ u.. ~.., r.v..,. <. B==. 0 v. :. =_v.v. =_ r. v =.s.= 1 5 u=stu=D. n =, e r.2-J. o .u m-v TEMPERATURE FOR TECH SPEC SHUTDOWN MARGIN. DO NOT GO BELO'4 THIS TDL3ERATURE. I 4 i f 1 t t

i i PREREOUISITES FOR NAT'JRAL CIRCUI.ATION f FOR T. 3Y AT LEAST 100 psi 1. PPZR>PcAi h o ipgg>T.3 ny.- er__g3i _0. a. a. ni ta

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T r. r. r r*T. "t..r U 4 u. a .~ VALIDITY OF THE INSTRL".ENT AS AN INDICATION OF S,e 1 1 n. r.t v-.4 i V.s l.r"- o, . w tiL 1vidf.v ~. - n u T..u r U.

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^ -. cm4.: 1.5.v. A nur vV -, 10 1 tJ INSTRU ENT BY: T "111. 41 ; L""M.a.Q. s(J. Y. i u O f ". f.3 "L U'W' T=T4~ T o ^ J nf.V.i a. ;. d. '.-

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7 i e i ra t : .1 L 1 PR.e.S q'L R? ? ?R Do rS q'L. e T.*.T.C-"sL" fr"4.n. T.O'.' .O..r q C. n v. D. S.A.S ? ip . v r *' r".:. "1 "U. r A I f i i I f l

CORDECTIVE ACTIONS TO ESTABLISH v 1rR.AL T -L r.o. su v nm..U.I o. Ae.u.,_r - e - r.m. e c cr T Vv.D

  • 14

_w 1. P C A IP OR T BY 100 PSI PZR SAT g 'oor Tp3g "O~i Go.a' ~t _R.u. a..; ' H 3v c r r a ENERGIZE ADDITIONAL PRESSURIZER HEATERS AND INCREASE PLA:;T PRESSURE INCREASE STD'! GENERATOR STEA'1 FLOW TO REDUCE PLANT TE'OERATURE 2. T I CMSUG C INCPIASE STEAM GE'!ERATOR STEA}! FLOW TO MAINTAIN PLANT TEMPEPATURE 3. STEAM GENERATOR LEVEL QUT OF NORMAL OPERATING RANGE LOW LEVEL - INCREASE FEEDWATER FLOW RATE AC z,u,A L : A,u... 7.. 3,., ---.s.. - c+r., D .u an.

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L: 1: za: ,Ly GH 7.s,v,a.t. - R.e 0 L.C : : -.Dr., ---anica : nr, r -, u a 'L, -n .u ALLOW LEVEL TO RETUP'; TO NOR.AL 4. PRESSURIZER LEVEL ABNOR:'.AL IF INDICATION IS VALID, ADJUST CHARGING A'iD .r.nn.,. -n n., . r.s. -., n 3 s.3 7 ~,<1 :. Lw t uv * *4 iv YKv. vDid .1 p.. Iu.,D, T.CA 2.r r :i3 v,,0 2, 3.: 7.D. C, nrrr_o-1.nv.u.23.u_, .rce r a. w v u _ HPSI PU'O A'ID/OR CHARGING PU'!PS TO ASSURE ADEQUATE INVENTORY

VEPIFICATION OF NATURAL CIRCULATION FLOW l. T -I. STEADY AT LESS THAN NORMAL FULL POWER 2T H C WITHIN 10 MINUTES OF TRIPPING REACTOR COOLANT PUMPS. 2. T. CONSTANT OR DECREASING WITHIN 10 MINUTES OF H SECL' RING REACTOR CCOLANT PU'f?S. (BOTH RTDS AND THER".OCOUPLES) 3. POWER TO FLOW RATIO: LESS THAN 1 (INDICATED BY iT POWER) 4. P CONTROLLED AT THE DESIRED VALUE PZR; IF NATURAL CIRCULATION CAN NOT 3E VERIFIED, TAKE APPROPRIATE ACTIONS TO ESTA3LISH PREREQUISITES. e =N

FORCED CIRCULATION OPERATION REACTOR TRIP REACTOR TRIP RCPs TRIP CONDITIONS SUGGEST TRIPPING ". ORE THAN ONE PU'4? PER LOOP '=S"'"*"~ Yes { "~ RCPs? TRIP T'io RCPs gg (OPPOSITE LOOPS) l' VERIFY NATURAL P P'~r T~r QU C ' ~ 7 C CIRCULATION? " " ~ ~ FOR NATURAL No Yes CIRCULATION' No Yes CORRECTIVE ACTION CORRECTIVE ACTION SATISFACTORY NAIUPAL 1 CIRCULATION? REMAINING RCPs Yes TRIP? Jo ,f e s s No C O.,.,.,,121:. 4 .ur ACTION CONTINUE FORCED CIRCULATION RESTART s.To Yee RCPs?

SATISFACTORY NATURAL CIRCULATION 1. T CONSTANT OR DECRF.ASING H LOOP RTDS AND CORE THERMCCCCPLES 2. T CONSTANT OR DECREASING C 3. T -I H C: LESS THAN THE NOR'd.AL FULL POWER 2T CONSTANT OR SI.0'.1Y VARYI'IG

  • SMALL, SHORT TERM VARIATIONS MAY RESULT FROM

= CHANGES IN STEA'I GE:iERATOR SECONDARY (I.E., ADDING FEEDWATER) 4. POWER TO FLOW RATIO: <1 (INDICATED BY "aT POWER") 5. STEAM GENERATOR LEVEL: NORMAL OPERATING RANGE 6. PPZR>PSA n FOR T.. SY 100 PSI PZR> T.d 3Y AT LEAST 200F 7. T 8. CHDIISTRY SAMPLE: TOTAL GAS CCNCENTRATION WITHIN a0Ru. n. _ e r: C T.. r.cn. r_c ssJ 9. PRESSURIZER LEVEL: NOR'3AL OPERATI'iG RANGE

.s CORRECTIVE ACTIONS FOR UNSATISFACTORY NATURAL CIRCULATION 1. IF MONITORING INDICATES ANY OF THE FOLLONING, NATURAL CIRCULATION IS NO LONGER SATISFACTORY AND CORRECTIVE ACTION MUST BE TAKEN TO RE-ESTA3LISH PREREQUISITES: A. P,, R IS APPROACHING P FOR T., Pc Sa.- n i B. T IS APPROACHING T pgg H C. T IS INCREASING C D. STEA'4 GENERATOR LE"EL IS OUT OF NOR".AL RANGE E. PRESSURIZER LEVEL IS OUT OF NORMAL RANGE 2. TH '" I C ARE INCREASING OR POWF.R TO FLOW RATIO IS H APPROACHING 1.0 INCREASE STEA'4 FLOW FROM STEA'4 GENERATOR CHECK STEAM GENER.-\\ TOR LEVEL. INCREASE FEED WATER IF REQUIRED 3. CHEMISTRY SA' ELE INDICATES OUT-OF-SPECIFICATION GAS CONCENTRATION START DEGASSING PROCEDURES es

MEETING

SUMMARY

DISTRIBUTION R. Mattson Meeting Attendees: R. Tedesco S. Newberry T Novak raves S. Hanauer R. Audette J. P. Knight R. Schoil D. Skovholt D. Vassallo W. Gammill R. '!allmer

5. Grimes A. Thadani J. R. Miller B. Clayton W. Kreger E. L. Conner V. " core M Ernst R. Denise L. Crocker Mr. W. H. House IE (3)

Bechtel Pcwer Corporation Gaithersbura~ Power Division ACRS (21) 15740 Shady Grove Rd. 6C PDR 3 Gaithersburg, M Cel Bunch (P-433) Mr. Charles B. Brinkman Combustion Engineering 4853 Cordell Ave. Bethesda, MD 20014 Mr. R. C. L. Olson Baltimore Gas & Electric Co. Gas & Electric Bldg., Room 922 P.O. Box 1475 Baltimore, MD 21203 =}}

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