ML17250A558

Responds to Dl Ziemann 800425 Ltr Re SEP Topics VI-10.A & VI-7.A.3 on Testing of Reactor Trip Sys & Engineered Safety Features Including Response Time Testing & ECCS Actuation, Respectively.Tech Specs & Test Procedures Encl

ML17250A558
Person / Time
Site:	Ginna
Issue date:	09/10/1980
From:	White L ROCHESTER GAS & ELECTRIC CORP.
To:	Crutchfield D Office of Nuclear Reactor Regulation
Shared Package
ML17250A560	List: ML17250A558 ML17250A562 ML17250A564 ML17250A567 ML17250A571 ML17250A574 ML17250A577 ML17250A578 ML17250A579 ML17250A581 ML17250A583
References
TASK-06-07.A3, TASK-06-10.A, TASK-6-10.A, TASK-6-7.A3, TASK-RR NUDOCS 8009160559
Download: ML17250A558 (9)

Text

REGULA Y INFORMATION OISTRIBUTIO SYSTEM (RIDS)ACCESSION NBR:8009160559 DOC~DATE;80/09/10 NOTARIZED:

NO FACIL:50-244ARobert Emmet Ginna Nuclear PlantP Unit iP Rochester G AUTH BYNAME AUTHOR AFFILIATION HHITEPL,O~, Rochester Gas L Electric Corp.RFCIP~NAME RECIPIENT AFFILIATION CRUTCHFIELD P 0~Doer ating Reactors Branch 5 NOTES:I cccv:SEP Sect.Lde.GROS.TD'R LP>R%Rg (AK7b<h'D$85 PILBS Pr FIED FIEOIA6 COPIES RECIPIENT LTTR ENCL ID CODE/NARK' 7 COPIES LTTR ENCL'ECIPIENT ID CODE/NAME ACTION: CRUTCHFIELD 04 INTERNAL: A/0 MATLLQUAL13 HYD/GEO BR 10 NRC PDR 0?G FIL 01 1 1 2 2 1 1 3 CONT SYS A 07 ILK 06 OR ASSESS BR 11 SEP BR 12 1 1 1 1 1

SUBJECT:

Responds to DL Ziemann 800ri?5 ltr re SEP Topics VI 10'VI 7.A.3 on testing of reactor trip sys 8 engineered safety features including response time testing 8 ECCS actuationP respectively.

Test procedures documentation encl.Sm B.8<tat,rrrDrPg<g

~+09/g 05'&DISTRIBUTION CDDE: AOSBS COPIES REiCEIVED:LTR Q ENCL'Q SIZE:gg TITLE: SEP Topics DOCKET¹05000244 05000244 EXTERNAL: ACRS NSIC 14 16 16 LPDR 03 05 1 1 1 1 8 580 3g TOTAL NUMBER OF COPIES REQUIRED: LTTR ENCL f~~.'1 h y 1 n a i W w A h lzisypi(uziesz lzzimldZ,~wzzu ROCHESTER GAS r ws~j.lL'tlLNM'/

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F~l~le(ND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y.14649 LEON O.WHITE, JR.VICK PRKSIDKNT TKLKPHONK amKA coos vis 546.2700 September 10, 1980 Director of Nuclear Reactor Regulation Attention:

Mr.Dennis M.Crutchfield, Chief Operating Reactors Branch 45 U.S.Nuclear Regulatory Commission Washington, D.C.20555

Subject:

SEP Topics VI-10.A and VI-7.A.3 R.E.Gonna Nuclear Power Plant Docket, No.50-244

Dear Mr.Crutchfield:

This letter is in response to a letter from Dennis L.Ziemann, NRC, to Mr.Leon D.White, Jr., RG&E, dated April 25, 1980, con-....q..;:-;: cerning SEP Topics VI-10.A,"Testing of Reactor Trip System and f;'r>-+~Engineered Safety Features, Including Response Time Testing," and;:;;-;.:"'-~/pl VI-7.A.3,"ECCS Actuation".

For convenience we have reproduced

';i,,fg)itIF each question with our answers.1.Provide information which discusses the response time testing to verify Reactor Trip System and Engineered Safety Feature response time.g~Res onse: The only response time testing performed at Ginna occurs during the Safeguards System Testing (enclosed are procedures RSSP-2.1"Safety Injection Functional Text," and RSSP-2.2"Diesel Generator Load and Safeguard Sequence Text").These tests are conducted to verify that the final actuated devices are properly operational within the times assumed in the plant design basis.2.The sdiveillance test frequency information is incomplete.

As shown on Tables 1 and 2, the test frequency on many items is not available.

Provide test frequency information in areas where this information is lacking.~Res onse: This information is provided in the attached Table l and Table 2.Ov 5'.Provide descriptive information on how the following actuation systems are being tested:)5 A.Auxiliary Feedwater Actuation System F C/'<6.'ak B.Main Steam and Feedwater Isolation Actuation System~ppp~(ke<~I~yy OZARK g+CP</~,i-Y-jjQ4 1 ROi,HESTER GAS AND ELECTRIC CORP.September 10, 1980 To Mr.Dennis M.Crutchfield, Chief.SHEET NO.R~es onse: The information requested is described in the enclosed procedures:

Procedure RSSP-1.5 Rev.6 (5 pages)Valve Interlock Verification

-Feedwater Isolation.

Procedure RSSP-2.1 Rev.13 (43 pages)Safety Injection Functional Test.Procedure RSSP-2.2 Rev.14 (22 pages)Diesel Generator Load and Safeguard Sequence Test.Procedure RSSP-3.0 Rev.7 (6 pages)Verification of Emergency Start Logic, Auxiliary Feedwater Pumps.4.RG 1.22 states that the protection system and the systems whose operation it initiates should be.designed to permit testing of the actuation devices during reactor operation.

The actuating equipment, not tested during reactor operation should be identified and justified to the provisions of position D.4 in RG 1.22.Most Engineered Safety Feature Systems in Ginna are only tested during refueling shutdown.Identify and justify the actuation logic and the actuated devices in the ESF Systems that are not tested during reactor operation.

R~es onse: The plant protection system has been designed to permit periodic testing to extend to and include actuation devices and actuated equipment whenever practicable.

While it is not possible to operate all actuation devices (such as trip of control rods)or significantly vary most of the operating parameters (such as coolant pressure)during operation, it is possible to test most equipment when the plant is in full power operation.

The bistable portions of the protective system (i.e., relays, bistables, etc.)provide trip signals only after signals from analog portions of the system reach preset values.Capability is provided for calibrating and testing the performance of the bistable portion of protective channels and various combinations of the logic networks during reactor operation.

The analog portion of a protective channel (i.e., sensors'and amplifiers) provides analog signals of reactor or plant parameters.

Checking the analog portion of a pro-tective channel is generally done by introducing and varying or substitute transmitter sz.gnal.Included for your information are the following test procedures:

ROCHESTER GAS AND ELECTRIC CORP.DATE September 10, 1980 To Mr.Dennis M.Crutchfield, Chief SHEET NO.5.PT-5.10, Process Instrumentation Reactor Protection Channel Trip test (Channel 1)PT-32.1, Plant Safeguard Logic Test A or B Train The listing of and justification for final actuated devices not, tested during power operation is in Section 4 of the Ginna Technical Specifications.

For the purpose of performing a test during reactor operation, each bypass condition should be individually and automatically indicated to the reactor operator in the max.n control room.Provide information on bypassed and inoperable status indica-tions and describe their application during the RPS logic test-ing and ESF channel and logic testing.R~es onse: During the RPS logic testing and ESF channel and logic testing, indication is automatically provided in the control room that the indi'vidual channel is under test.The protective channel being tested is placed in the"trip" mode, so that there z.s no loss of redundancy.

If during testing any final actuated devices are taken out of service (e.g., put into"pull-stop"), this condi-tion is indicated on the control room by means of test tags.6.Provide information which discusses the testing of containment air recirculation, cooling, and filtration systems.~Res onse: The following procedures are provided for information:

Procedure PT-2.3.1 Rev.5 (8 pages)Post Accident Char-coal Filter Dampers.Procedure PT-25 Rev.3 (4 pages)Containment Post Accident Charcoal Filter By-Pass Flow.Procedure PT-26 Rev.2 (7 pages)Containment Fan Recir-culation Unit Data Filter Bank Testing.Procedure PT-37.5 Rev.0 (10 pages)Containment Recir-culation Fans Mass Air Flow Check.7.Provide information which discusses the testing of contain-ment isolation systems.

r h C/4RORHESTER GAS AND ELEC RIC CORP.DATE September 10, 1980 Mr.Dennis M.Crutchfield, Chief SHEET NO.R~es onse: Containment isolation is tested during the Safety In-jection Functional Test, this procedure is provided for, your information.

Three copies of this information package are provided.'Very'truly yours,