ML20155K432

Forwards Addl Info Re Paragraphs 1.2 & 4.3 of Generic Ltr 83-28, Required Actions Based on Generic Implications of Salem ATWS Events, Per 860409 Request & SER Open Item 5. Post-trip Review (Data & Info Capability) Discussed

ML20155K432
Person / Time
Site:	Vogtle
Issue date:	05/23/1986
From:	Bailey J GEORGIA POWER CO., SOUTHERN COMPANY SERVICES, INC.
To:	Youngblood B Office of Nuclear Reactor Regulation
References
0492V, 492V, GL-83-28, GN-916, NUDOCS 8605280159
Download: ML20155K432 (6)

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'V-~+ Georgia Power Company Route 2. Box 299A Waynesboro, Georgia 30830 Telephone 404 554 9961 404 724-8114

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Southern Company Services. Inc.

Post Office Box 2625 Dirmingham, Alabama 35202 Telephone 205 870-6011 Vogtle Proj.ect May 23, 1986 Director of Nuclear Reactor Regulation File: -X6BK10 Attention: Mr. B. J. Youngblood Log: GN-916 PWR Project Directorate #4 Division of PWR Licensing A U. S. Nuclear Regulatory Commission Washington, D.C. 20555 REF: REQUIRED ACTIONS BASED ON GENERIC IMPLICATIONS OF SALEM ATWS EVENTS (GENERIC LETTER 83-28)

NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 /.ND CPPR-109 V0GTLE ELECTRIC GENERATING PIANT - UNITS 1 AND 2 SER OPEN ITEM St GENERIC LETTER 83-28

Dear Mr. Denton:

In a telephone conversation with your staff on April 9,1986 additional information was requested in paragraph 1.2 of the referenced letter.

Attachment A contains the requested information. In a later telephone call, April 24, 1986, your staff requested additional information concerning paragraph 4.3 of the referenced letter. ' Attachment B contains this information.

Should you have any questions, please inquire.

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Sincerely, J. A. Bailey Project Licensing Manager JAB /sm xc R. E. Conway G. Bockhold, Jr.

R. A. Thomas D. C. Teper J. E. Joiner, Esquire W. C. Ransey B. W. Churchill, Esquire NRC Resident Inspector M. A. Miller (2) L. T. Gueva B. Jones, Esquire Vogtle Project File 0492V '

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ATTACHMENT A GENERIC LETTER 83-28 1.2 POST-TRIP REVIEW (DATA AND INFORMATION CAPABILITY)

THE FOLLOWING IS A TABLE LISTING V0GTLE's OPTIONS FOR POST-TRIP REVIEW DATA. QUALIFIED REVIEW DATA MEDIA ARE SHOWN AS "YES" IN THE COMPARISON TABLE. THOSE- INDICATED AS "N0" ARE NOT AVAILABLE FOR THE MEDIA LISTED.

V0GTLE PLANS TO EITHER USE THE PROTEUS OR ERF OPTION AS SEPARATE AND QUALIFIED MEDIA. THE CONTROL ROOM RECORDER STRIP CHARTS WILL BE USED TO COMPLETE AN OPTION.

PROTEUS OPTION:

V0GTLE PLANS TO USE THE PROTEUS TREND AND TRIP LOGS AS THE PRIMARY REVIEW DATA MEDIA SINCE PROTEUS IS QUALIFIED AS SHOWN IN THE TABLE WITH THE FOLLOWING JUSTIFICATION.

JUSTIFICATION:

A. THE ERF SPDS IS AVAILABLE TO MANUALLY INITIATE A HARD COPY PRINT 0UT OF THE FOLLOWING TO MAKE THE PROTEUS OPTION COMPLETE:

1. PRESSURIZER PRESSURE VS. PORV POSITION TREND

2. CONTAINMENT RADIATION

3. CONTAINMENT LEVEL B. NOTE 1.

ERF OPTION:

THE ERF OPTION APPEARS TO MEET ALL THE CRITERIA EXCEPT FOR CONTROL R0D POSITION. THERE ARE NO PLANS TO ADD THIS TO THE ERF SINCE R00 POSITION RELATIVE TO THE OTHER PARAMETERS /ACTUATIONS LISTED DOES NOT PROVIDE ANY ADDITIONAL INFORMATION THAN WHAT IS PROVIDED BY NEUTRON FLUX.

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REVIEW DATA MEDIA SEQUENCE OF ANALOG TIME EVENTS HISTORY (SOE)

ERF PROTEUS ERF PROTEUS CONTROL ROOM TREND LOG TRIP LOG RECORDER REVIEW CRITERIA:

TIME DISCRIMINATION YES YES NA NA YES

<100m SEC: (NOTE 3) (ImSEC)

SAMPLING NA NA YES YES YES INTERVAL >10 SEC: (2.5 SEC) (10 SEC)

UPDATE:

5 MIN. PRE-TRIP: YES YES YES YES YES (NOTE 2) ONGOING (2 HRS.) (400 SEC) UNLIMITED 10 MIN. POST-TRIP YES YES YES YES YES (2 HRS.) ONG0ING (2 HRS.) (NOTE 1) UNLIMITED RECORD MEDIA:

PRINT 0UT: YESO YES YESO YES NA TAPE: YES N0 YES N0 NA COPY AVAILABLE: YES N0 YES N0 YES (STRIP CHART)

POWER SOURCE:

UPS(BATTERYBACKED) NIE NIE NIE NIE 1E&NIE PARAMETERS /ACTUATIONS:

REACTOR TRIP YES YES NA NA NO SAFETY INJECTION YES* YES NA NA NO CNTMT ISOLATION YES* N0 NA NA N0 TURBINE TRIP YES YES NA NA NO CONTROL R0D POS N0 N0 N0 YESO N0 NEUTRON FLUX, POWER NA NA YES YES YES CNTMT PRESSURE NA NA YES YES YES CNTMT RADIATION NA NA YES NO# NO CNTMT SUMP LEVEL NA NA YES N0# YES RCS PRESSURE NA NA YES YESO YES RCS TEMPERATURE NA NA YES YES YES PRZR LEVEL NA NA YES YES YES RCP STATUS YES YES NA YES(F) (ES(RCS F)

RCS FLOW NA NA YES YES YES SI FLOW NA NA YES YESO YES

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- OR -

SI VALVE & PUMP YES* N0 NA NA N0 STATUS SG PRESSURE NA NA YES YES YES SG LEVEL NA NA YES YES YES FEED FLOW NA NA YES YES YES STEAM FLOW NA NA YES YES YES AFWS FLOW NA NA YES YES@ NO

- OR -

AFW VALVE & PUMP. YES YES NA NA NO (PUMP ONLY)

-AC VOLTAGE NA NA YES YES0 NO DC VOLTAGE NA NA YES YES0 NO D/G STATUS NA NA YES YES N0 (KWorV) (KW)

PORV POSITION YES N0# NA NA NO INFORMATION GATHERED FOR THE ' POST TRIP REVIEW SHALL BE MAINTAINED FOR THE DURATION OF THE PLANT OPERATING LICENSE IN ACCORDANCE WITH THE VEGP TECHNICAL SPECIFICATIONS.

NOTE 1.

THE PROTEUS TRIP LOG ONLY MEETS CRITERIA FOR DATA COLLECTION 10 MINUTES AFTER A TRIP IF THE OPERATOR MANUALLY INITIATES THE LOG AT 10 MINUTES INTO THE EVENT, SINCE THE TRIP AUTOMATICALLY INITIATES AND HAS STORAGE 400 SECONDS BEFORE AND AFTER THE TRIP. A MANUAL INITIATION ACTS THE SAME AS A TRIP, BUT WITH A DIFFERENT INITIATION TIME. V0GTLE's PROTEUS TIME DISCRIMINATION, SAMPLING INTERVAL, AND UPDATE TIME IS TYPICAL OF THE GENERIC WESTINGH0USE DESIGN USED AT SIMILAR PWRs.

NOTE 2.

THE ERF SEQUENCE OF EVENT (S0E) LOG WILL HAVE THE CAPABILITY TO STORE AT LEAST A 5 MINUTE UPDATE PRE-TRIP SINCE IT STORES THE PREVIOUS 2048 CONTACT CHANGES FROM A FIELD OF APPROXIMATELY 750 ACTUATIONS FROM A PREVIOUS 2 HOUR PERIOD.

NOTE 3.

THE ERF COMPUTER MEETS THE 1 MSEC TIME DISCRIMINATION CRITERIA FOR PARAMETERS / CONTACTS LISTED AS YES UNDER THE SOE ERF COLUMN. THOSE LISTED AS "YES*" HAVE A 2.5 SECOND TIME DISCRIMINATION SINCE THEY PASS THROUGH THE PLANT STATUS MONITORING SYSTEM (PSMS) REACTOR PROTECTION UNITS (RPUs). NOT ALL THE SI VALVES MEET THE 1 MSEC CRITERIA; HOWEVER, THERE ARE OTHER INDICATIONS TO VERIFY SI ACTUATION SUCH AS SI FLOW AND ALIGNMENT OF SOME SI VALVES.

CONTAINMENT ISOLATION ACTUATION IS ALSO ACTUATED BY A SI ACTUATION AND VEGP FEELS THAT THE SI ACTUATION INDICATIONS GIVEN AB0VE ARE SUFFICIENT TO PROVIDE THE 1 MSEC TIME DISCRIMINATION WHEN A 2.5 SEC TIME ' DISCRIMINATION IS ALSO AVAILABLE FOR CONTAINMENT ISOLATION ACTUATION.

9 DEN 0TES THAT THE ITEM IS NOT CURRENTLY IN THE LOG BUT THE ITEM HAS AN INPUT TO PROTEUS AND WE PLAN TO ADD THESE FEATURES.

1. DEN 0TES THAT EVEN THOUGH THE PARAMETER / ACTUATION ITEM IS LISTED AS NOT MEETING THE GENERIC LETTER REVIEW CRITERIA FOR THE PROTEUS OPTION, AN ALTERNATE MEDIA, USING THE ERF TREND HARDCOPY, MEETS THE CRITERIA.

• DEN 0TES THAT THOSE LISTED AS "YES*" HAVE A 2.5 SECOND TIME DISCRIMINATION SINCE THEY PASS THROUGH THE PLANT STATUS MONITORING SYSTEM (PSMS) REACTOR PROTECTION UNITS (RPUs).

ATTACHMENT B l

l GENERIC LETTER 83-28, ITEM 4.3 CLARIFICATION TO POSITION INDICATION CIRCUITRY OF REACTOR TRIP AND BY-PASS BREAKERS VEGP Reactor Trip Breakers could be placed in either of the four following positions:

1 - CONNECTED POSITION 0 main power is connected 0 cell switch actuating fingers are connected 0 aux, contacts are connected 2 - TEST POSITION 0 main power is disconnected 0 cell switch actuating fingers are disconnected 0 aux. contacts are connected 3 - DISCONNECTED POSITION 0 The main power, cell switch actuating fingers and auxillary contacts are disconnected 4 - REMOVED POSITION 0 The main power, cell switch actuating fingers and auxilliary contacts are disconnected.

' All four Reactor Trip and By-pass Breakers have closed and Open Position Indication on the Main Control Board. For Both Reactor Trip Breakers, position indications are shown when breakers are either in connected or in test position. Cell Switch Contacts are not used to power the indication or trip circuits.

In the case of By-Pass Breakers, positions indications are shown only when the breakers are in connected position. Power for position indication and Remote Shunt Trip are fed tnrough Cell Switch Contacts.

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