ML20206N479

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Forwards RAI Re 980529 Amend Request for Byron & Braidwood to Credit Automatic PORV Operation for Mitigation of Inadvertent SI at Power Accident.Response Requested 60 Days After Receipt Date
ML20206N479
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 05/13/1999
From: John Hickman
NRC (Affiliation Not Assigned)
To: Kingsley O
COMMONWEALTH EDISON CO.
References
TAC-MA2043, TAC-MA2044, TAC-MA2048, TAC-MA2049, NUDOCS 9905170241
Download: ML20206N479 (4)


Text

.

,May.13, 1999,

Mr. Oliver D. Kingsley, President Nuclear Generation Group

' Commonwealth Edison Company l

Executive Towers West lil

- 1400 Opus Place, Suite 500 -

Downers Grove, IL 60515

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - BYRON STATION, UNITS 1 AND 2 AND BRAIDWOOD STATION, UNITS 1 AND 2 (TAC NOS. MA2043, MA2044, MA2048 AND MA2049),

Dear Mr. Kingsley:

By letter dated May 29,1998, Commonwealth Edison Company (Comed) submitted an i

amendment request for Byron and Braidwood to credit automatic power-operated relief valve I

(PORV) operation for mitigation of inadvertent safety injection at power accident. Subsequently, Comed requested incorporation of this amendment into the improved standard technical I

specification (ISTS) implementation. Following several conference calls between the staff and Comed, it became apparent that the staff had issues which could not be resolved prior to ISTS implementation and the review of this request was deferred. Enclosed is a request for I'

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additional information documenting the staff's concerns. These questions were discussed with members of your staff on April 30,1999. It was agreed that the responses would be provided 60 f

days after receipt.

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h h[gineerely, priginal signed by mS John B. Hickman, Project Manager Project Directorate ill-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. STN 50-454, STN 50-455, DISTRIBUTION:

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STN 50-456, STN 50-457 PUBLIC PDill r/f JZwolinski/SBlack CThomas/AMendiola s

Enclosure:

As stated CMoore JHickman SBailey MJordan, Rlll cc w/ encl: See next page OGC,015B18 ACRS, T2E26 JMav k, HICB

. DOCUMENT NAME: G:\\PD3-2\\CM\\ BRAID-BY\\LTRA2043.WPD SEE PREVIOUS CONCURRENCE *

. Ta receive a copy of this document, Indicate in the box: "C" = Copy without enclosures "E" = Copy with enclosures *N" = No copy OFFICE PM:LPD3 P LA:LPD3 urv PM:LPD3 6

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DATE.

05/ / o /99 9905170241 990513 PDR ADOCK 05000454 P

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e 0, Kingsley Byron /Braidwood Stations Commonwealth Edison Company j

cc:

Ms. C. Sue Hauser, Project Manager Attomey General Westinghouse Electric Corporation 500 S. Second Street Energy Systems Business Unit Springfield, Illinois 62701 Post Office Box 355 Pittsburgh, Pennsylvania 15230 lilinois Department of Nuclear Safety Office of Nuclear Facility Safety Joseph Gallo 1035 Outer Park Drive Gallo & Ross Springfield, Illinois 62704 1025 Connecticut Avs., N.W., Suite 1014 Washington, DC 20036 Commonwealth Edison Company Byron Station Manager Howard A. Leamer 4450 N. German Church Road Environmentallaw and Policy Byron, Illinois 61010-9794 Center of the Midwest 35 East Wacker Dr., Suite 1300 Commonwealth Edison Company Chicago, Illinois 60601-Site Vice President - Byron 4450 N. German Church Road U.S. Nuclear Regulatory Commission Byron, Illinois 61010-9794 Byron Resident Inspectors Office 4448 N. German Church Road U.S. Nuclear Regulatory Commission Byron, Illinois 61010-9750 Braidwood Resident inspectors Office RR 1, Box 79 Regional Administrator, Region lll Braceville, Illinois 60407 U.S. Nuclear Regulatory Commission 801 Warrenville Road Mr. Ron Stephens

' Lisle, Illinois 60532-4351 lilinois Emergency Services and Disaster Agency Ms. Lorraine Creek 110 E. Adams Street

. RR 1, Box 182 Springfield, Illinois 62706 Manteno, Illinois 60950 Chairman

. Chairman, Ogle County Board Will County Board of Supervisors Post Office Box 357 Will County Board Courthouse Oregon, Illinois 61061 Joliet, Illinois 60434 Mrs. Phillip B. Johnson Commonwealth Edison Company 1907 Stratford Lane Braidwood Station Manager Rockford, Illinois 61107 RR 1, Box 84 Braceville, Illinois 60407-9619 George L. Edgar Morgan, Lewis and Bochius 1800 M Street, N.W.

Washington, DC 20036 r

s O. Kingsley Byron /Braidwood Stations Commonwealth Edison Company Ms. Bridget Little Rorem Commonwealth Edison Company j

- Appleseed Coordinator Reg. Assurance Supervisor-Braidwood 117 N. Linden Street RR 1, Box 84 Essex, Illinois 60935 Braceville, Illinois 60407-9619 Document Control Desk-Licensing Commonwealth Edison Company Commonwealth Edison Company Reg. Assurance Supervisor-Byron 1400 Opus Place, Suite 400 4450 N. German Church Road Downers Grove, Illinois 60515 Byron, Illinois 61010-9794 Commonwealth Edison Company Ms. Pamela B. Stroebel Site Vice President - Braidwood Senior Vice President and General Counsel RR 1, Box 84 Commonwealth Edison Company Braceville, Illinois 60407-9619 P.O. Box 767

)

Chicago, Illinois 60690-0767 Mr. David Helwig Senior Vice President i

Commonwealth Edison Company i

Executive Towers West 111

{

1400 Opus Place, Suite 900 l

Downers Grove, Illinois 60515 Mr. Gene H Stanley PWR Vice President Commonwealth Edison Company Executive Towers West lll 1400 Opus Place, Suite 900 Downers Grove, Illinois 60515 Mr. Christopher Crane BWR Vice President Commonwealth Edison Company Executive Towers West til 1400 Opus Place, Suite 900 Downers Grove, Illinois 60515 Mr. R M. Krich Vice Presdient - Regulatory Services Commonwealth Edison Company Executive Towers West 111 1400 Opus Place, Suite 500 Downers Grove, Illinois 60515

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REQUEST FOR ADDITIONAL INFORMATION REGARDING BYRON STATION. UNITS 1 AND 2 AND BRAIDWOOD STATION. UNITS 1 AND 2 CHANGE TO CREDIT AUTOMATIC POWER-OPERATED RELIEF VALVE (PORV)

OPERATION FOR MITIGATION OF INADVERTENT SAFETY INJECTION AT POWER ACCIDENT The following documents the basis for the staff's concems that the Byron /Braidwood design does not meet the required single failure criterion.

On November 11,1998, Comed provided a set of seven drawings (6E-1-4031RY32,01,15,26, 16,4030RY13,17] in which the class 1E portion of pressure transmitter 1PT-0455 signal to the PORV solenoid 1RY455A was shown in yellow and the non-1E portion was shown in orange.

The circuit shown by these two colors indicates that the safety signal from the class 1E transmitter and the isolation relay goes through a series of non-1E devices including relay PY455EX, whose output contact is considered class 1E, to initiate an automatic actuation of the associated PORV solenold. An additional set of two drawings [6E-1-4031RYO4,13] for the signal from pressure transmitter 1PT-0458 was also provided with similar color scheme. This l

set, however, does not indicate actuation of a PORV solenoid.

I The instrumentation circuit for an automatic operation of a PORV to mitigate the consequences of an inadvertent safety injection (SI) should meet the requirements set forth in IEEE-279 as required by 10 CFR 50.55a for protection systems. IEEE-279 explains design requirements for control and protection system interaction in section 4.7 and the single failure criterion in section 4.2. As per section 4.7.2 of IEEE 279, an isolation device is used to transmit a signal from protective system equipment for control system use such that no credible failure at the output of the isolation device, i.e., no failure or fault in the non-1E portion of the instrumentation circuit, shall affect the protective function of the associated class 1E system.

The isolation devices shown on the submittal drawings do not perform the function identifed in section 4.7.2 of IEEE-279 and failure or a fault in any one of the several non-1E devices in the non-1E portion of the circuit will prevent automatic actuation of the PORV solenoid. Therefore, the circuit initiating automatic actuation of the PORV solenoid should, in its entirety, meet the single failure criterion of IEEE-279. Please address this issue. Incidently, the Salem Generating Station design involved similar problems of not meeting the single failure criterion in the automatic actuation circuit of its PORVs. The licensee incorporated several design modifications to meet the regulations.

An additional issue, unrelated to the single failure issue, concems a data plot provided on November 18,1998. Specifically, Figure 4, which plotted Pressurizer Water Volume, shows a 8

high value of approximately 1870 ft. However, Table 5.4-9 in the Updated Final Safety Analysis Report (UFSAR) documents the internal volume of the pressurizer as 1800 ft. This discrepancy 8

will need to be resolved.

ENCLOSURE