ML18219E086

Submit First Supplement Dated 3/8/1976 to Startup Test Report Which Covers Startup Test Report Sec. 7.5.1 Shutdown from Hot Shutdown Panel

ML18219E086
Person / Time
Site:	Cook
Issue date:	03/15/1976
From:	Hunter R American Electric Power Service Corp
To:	James Keppler NRC/RGN-III
References
Download: ML18219E086 (26)

Text

NRC FORhI 'l95

{2.76)

U.S. NUCLEAR REGULATORV Co, "SS ION DOCKET NUMBER 50-

/5 NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL FILE NUMBER Mr Keppler NLETTER NOR IGINAL OCCAM v DESCRIPTION ClNOTORIZED

%UNCLASSIFIED PROP American Electric Pwr Svc Cor New Yoxk, NY R

S Hunter INPUT FORM ENCLOSURE DATE OF DOCUMENT 3-15-76 DATE RECEIVED3 22 7{)

NUMBER OF COPIES RECEIVED none signed Ltr trans the following:

Supplement ffl to Start-up'eport (Original rpt dtd 3-8-76)....(30 cys encl rec'd)

PLANT NAME:

Cook 81 SAFETY ASSXGNED AD:

BRANCH CHIEF:

FOR ACTION/INFORMATION ASSIGNED AD:

BRANCH CHIEF

~

ENVXRO 3<<23-6 eh PROJECT MANAGER;

c. io PROJECT MANAGER.

LIC~ ASST REG FILE NRC PDR E

S INTERNALDISTRI BUTION ERNST X&E GOSSXCK & STAFF PROJECT MANAGEMENT BOYD P,

COLLINS HOUSTON PETERSON MELTZ HELTEMES SKOVHOLT LPDR ~ S

{ISt EN NEER N KNIGHT SIHMEIL PAHLICKX REACTOR SAFETY ROSS NOVAK

'OSZTOCZY CHECK AT & I SALTZMAN RUTBERG EXTERNALDISTRIBUTION NATL.LAB BENAROYA IPPOLXTO OPERATING REAC ORS STELLO OPERATING TECH EISENHUT SHAD BARR SCHIPENCER GRIMES SITE SAPETY R~ENV R ANALYSIS DENTON & MULLER BROOKHAVEN NATL LAB ALLARD SPANGLER SITE TECH GAMMILL STEPP HULMAN SITE ANALYSIS VOLltIER BUNCH J ~ COLLINS KREGER CONTROL NUMBER TIC ASLB NRC FOIIM 196 {2.76)

SE REG. V-IE LA PDR CONSULTANTS II LA Di ULRIKSON(ORNL) 2PZ

C

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,I AMERICAN ELECTRIC PONKR S e rvi c e Co rp o r t

2 Broadfoay, Nno York, N. Y. 10004

'212) d22.4800

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/c ROBERT S. HUNTER Piet Prtsidtn! -Ãneltar Engineering March 15, 1976 Donald C.

Cook Nuclear Plant Unit No'1 Startup Test Report Docket No. 50-315 License No.

DPR-58 Mr. J'.

G. Keppler, Regional. Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region IIX 799 Roosevelt Road Glen Ellyn, Illinois 60137 i

Dear Mr. Keppler:

tt,$, ~CrE/,g ef M'w>a}oA hleil tedidg w Pj In complianc'e with Regulatory Guides 1.16 and 10.'1, we are'ending you two (2) copies of the first supplement, dated March 8, 1976> to our Startup Test Report for the Donald C.

Cook Nuclear Plant Unit 1.

This supplement covers Startup Test Report Section 7.5.1 "Shutdown From Hot Shutdown Panel."

Twenty-five i'25I copies are being sent to Dr. Ernst Volgenau, Director, Office of. Inspection and.

Enforcement.

Two (2) copies are'being sent to Mr. N. G. McDonald, Director, Office of. Management information and Program Control.. Thirty (30) copies

.are also being sent to Mr. R. A. Benedict, Licensing Project Manager for the Donald C.. Cook.Nuclear Plant,:Directorate of Licensing.

~

Very truly'yours, RSH:mam Enclosure R. S. Hunter cc:

see next page

I J.

G. Keppler

'4 March 15, 1976 cc:

E. Volgenau, Director,'.E.

(25)

W.

G. McDonald, Director, M.I.P..C. (2)

R. A. Benedict (30)

G. Charnoff (1)

R;. C. Callen (1)

R. J. Vollen (1)

P.. W. Steketee (1)

R. Walsh (1)

R.

W. Jurgensen (1)

DONALD C ~

CO NUCLEAR PLANT UNIT gl STA TUP TEST REPORT SECTION 7.5.I SHUTDOWN FROM HOT SHUTDOWN PANEL PURPOSE The objective of the Shutdown from Hot Shutdowm Panel test was to demonstrate the abil liy of maintaining the reactor in the hot standby mode from the Hot Shutdown Panel.

SUMMARY

OF RESULTS During the reactor trip and operation from the Hot Shutdown Panel, the fol lowing parameters were monitored and recorded:

pressurizer

pressure, pressurizer level, steam generator level,auxil fary feedwater flow and main steam pressure.

The recorder charts, Figure 7.5. I-I through Figure 7.5. I-7,

'ndfcate only normal transients were present following the reactor trip and

'uring the hot standby operation from the Hot Shutdown Panel and ihe para-meters were maintained within the allowable tolerances.

DISCUSS ION OF TEST The Shutdown from the Hot Shutdown Panel test was performed on October II, 1975.

The initial conditions prior to the reactor trfp and the test are listed 'in Table 7.5.I-I.

Communications were established

'between the main control room and the hot shutdown panel with test tele-phones.

All indicators located on the hot shutdown panel were compared with the indication located in the main control room and were fn agree-ment, prior to the test.

An operator, located at the turbine, manually tripped the turbine, which resulted in ihe reactor trip, at 23I9 hours.

The turbine trip/reactor trip provided the simulated emergency trip which would be required during an actual emergency shutdown operation from the hot shutdown panel.

Reactor trip indication was received from the solid state protection system indication lights provided on the hot shutdown panel.

At 2325 hours0.0269 days <br />0.646 hours <br />0.00384 weeks <br />8.846625e-4 months <br />, steam generator level, wide range indication was 60$ and the first system controls were transferred to the hot shutdown panel.

Until this time, all system controls were in automatic, controlling from the main control

room, and operator action was not required either fn the main control room or at the hot shutdown panel.

The auxiliary feed-water controls transferred to the hoi shutdown panel and manual operation at the hot shutdown panel maintained the steam generator levels.

Emergency boration was demonstrated operable from the hot shutdown panel at 2342 hours0.0271 days <br />0.651 hours <br />0.00387 weeks <br />8.91131e-4 months <br /> (a boration flow of 75 gpm and charging flow of IIO gpm were indicated on the hot shutdown panel).

The auxiliary feedwater system control was returned to the main control room at 2346 hours0.0272 days <br />0.652 hours <br />0.00388 weeks <br />8.92653e-4 months <br /> after satisfactory hot standby opera-tion from the hot shutdown panel was demonstrated.

Operational verification of the remaining hot shutdown panel controls proceeded on an individual control circuit basis shile maintaining communications with the control room.

Essential service water, nonessential service water, and component cooling water pumps and their associated valves were cycled and performed properly.

Initial testing of the controls of the Hot Shutdown Panel was performed under peroperationai test P0-050-598.

3/8/76

During the verification of power relief valves MRV-2I3 and MRV-243, the valves failed to respond.

An emergency Job order was generated to resolve the problem.

The failure of MRV-2I3 and MRV-243 to respond was traced to a control air supply valve, which was closed.

The power relief valves were then demonstrated operable.

Numerous indicating lights on

.the hot shutdown panel required replacement during the test.

Appendix A ls comprised of plant process recorder charts lndlcatlng ihe response of Tavg, Tref, overpower, overtemperaiure hT setpoints, feed pump pressures, reactor coolant loop temperatures, control air flow, and trip sequence monitor during the reactor trip and hot standby operation from the hot shutdown panel.

TABLE 7.5.1-1 TEST lNITIALCONDITlONS

1. 'uclear lnstrumentatlon System Power Level N-41 29$

N-42 29$

N-43 29$

N-44 29$

2, Reactor Coolant Loops

$ hT Power Tavg oF No.

1 30$

550 No. 2 32$

550 No. 3 550 No.

4 31$

550 Steam Generators No.

1 Narrow Range 5 Level 43$

Steam Flow (pph) 0.9xlOs No. 2 435 0.9x10s No.

3 43$

0.9xlOs No.

4 43$

0.9xlOs 4.

Pressurizer Level 29$

5.

Pressurizer Pressure 2230 psig 6.

East Centrifugal Charging Pump in operation; Charging Flow 80 gpm.

7.

Letdown Flow Path QRV-162, Letdown Flow 73 gpm 8.

No.

2 Boric Acid'ump operating in fast speed.

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APPEND I X A Figure Number Descrl tlon 7.5.1-9 7.5.1-10

7. 5. I-I I

'7.5.1-12 7.5.1-13 7.5.1-14 7.5.1-15 7.5.1-16 7.5.1-17 7.5.1-18 Turbine First Stage'ressure and Main Steam Pressure Tref and Tavg Loop 2, 5 hT, Overpower and Overtemperature Reactor Trip Setpolnts Feedpump Suction and Discharge Pressures Loop No. I Reactor Coolant Temperatures Loop No. 2 Reactor Coolant Temperatures Loop No. 3 Reactor Coolant Temperatures Loop No. 4 Reactor Coolant Temperatures Control Air Flow Trip Sequence Monitor Printout

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~ ~ 2S4 2238 2S4 2322 'S4 2322 2S4 2322 2S4 2322 284 2322 284 2322 28 4 2322 284'322 2S4 2322 234 2322 284 2322 2S4 2322 284 2322 284 2322 2S4 2322 284 2322 2S4 2322 284 2322 2S4 2322 284 2322 2S4 2322 284 2322 284 2322 284 2322 284 2322 284 2322 284 2327 284 2327 28 4 2327 284 2338 284 2335 284-2336 284 2336 284 2336 284 2336 2S 4 2336 284 2336 28 4 2336 2S 4 2336 284 2336 284 2336 284 2336 2S4 2336 284 2336 284 2336 2S4 2336 284 2348 284 2348 284 2348 28 4 2348 284 2343 2S4 2343 16 869 16 814 17 47S 17 498 17 458 17 488 17 493 17 498 17 414 17 473 17 736 17 888 18 829 18 437 19 851 35 775 47 493 47 488 47 467 47 478 47 486 48 427 4S 848 49 884 58 421 59 455 51 828 53 334 55 496 88 481 57 464 88 823 81 849 82 465 84 764 85,888 87 856 89 882 15 317 16'48 28 499 23 848 26 489 27 372 27 481 34 318 89 839 46 458 47 748 58 774 41 838 oi61 T 888 A 148 A 141 A 844 A 845 A 127 A 126 A 156 A 847 A 846 A 112 A 118 A 113 A 829 A 137 A 873 A 817 A 163 A 157 A 158 A 159 A 156 A 145 A 147 A 817 A 151 A 162 A 146 A 14S A 145 T 888 A 826 A 826 A 826 A 826 A 826 A 826 A 826 A 826 A 825 A 825 A 825 A 825 A 825 A 825 A 825 A 825 A 826 A 826 A 826 A 826 A 896 A 118 MECH TRI P OPER 4 )g, EMG GOV OVSP TnP REACT BKR TRI P A REACT BKR TRI P B. MT REHEAT. VA CL MT STOP VA CL GENERAT MOTORI NG REACT BKR UV B REACT BKR UV A FPTW VACUUM TRIP FPTW HYDR PR LOLl FPTiJ OVSP TRP OP RT PWRG HI RATE TR EH C TRI P SYS TRP HTR 1A LEVEL HI RT SG2 LEV EX LO TRBVA TRPOA DIFF'VALL DI FF OP ER UNI T DI FF OPER ALTERX DIFF OPER G EN ERAT MOTORI N G DC BRG OI LPP RUN TRB 0 IL BUPPP RUN RT SG2 LEV EX LO GEN COOL FLOW LO GEN COOL TRP OP ER DC BRG OI LPP FAIL TRB OILBUPPP FAIL DC BRG OILPP PUN DCCOOK 1 TEST POINT RT INTERMRGL EV TR PT INTERMRGLEV TP. RT I NTERMRG1. EV TR RT INTERMRGLEV TR. RT INTERMRGLEV TR RT INTERMRGLEV TR RT INTERMRGLEV TR RT INTERMRGLE'J TR'T SOURCERGLEV TR RT SOURCERGLEV TR RT SOURCERGLEV TR RT SOURCERGLEV TR RT SOURCERGLEV TR RT SOURCERGLEV TR RT SOURCERGLEV TR RT SOURCERGLEV TR RT I NTEPMRGLEV TR RT INTERMRGLEV TR RT INTERMRGLEV TR RT INTERMRGLEV TR FPE SUCT PR TRI P FPW SUCT PR TRI P FIGURE 7.5.1-18 TRIP SEPUENCE MONITOR PRINTOUT

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