ML20206A953

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Summary of 870318 Meeting W/Util Re Hydrogen Recombiner Capability.Util Agreed to Submit Tech Specs for Nitrogen Sys Pressure & Nitrogen Switchover Function by 870327.Generic Ltr 84-09 & NRC 861030 Safety Evaluation Also Discussed
ML20206A953
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 04/03/1987
From: Sylvester E
Office of Nuclear Reactor Regulation
To:
NRC
References
GL-84-09, GL-84-9, NUDOCS 8704080247
Download: ML20206A953 (5)


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April,3.-1987

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N '7 4 Dockets Nos.;50'-325/124'- '

N f LICENSEE: CarolinaPower&LightCompany-(CP&L).

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FACILITY:' Brunswick Steam Electric Plant, Units 1:and 2. ~

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!SUBdECTLSUhAkYOFMEETINGHELDONMARCH.1'8,1987: HYDR 0 GEN RECOMBINER \

CAPABILITY- -

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t Backgrou'nd) ,

- I Discussions were' held with the CP&L staff regarding the'need for Technical

' Specifications (TS) -to ensure the operability of the nitrogen switchover.

portion.of the _ Brunswick facility instrument air system. The list of

, . attendees is'provided in;the enclosure.

By . letter ' dated May- 8,J1984, the'NRC issued Generic Letter 84-09, "Recombiner Capability Requirements of 10 CFR 50.44(c)(3)(ii)" .to clarify the conditions  ;

- that would preclude the need for' a hydrogen recombiner capability at some s reactor plants.; Criteria were provided to ensure that the amount of oxygen that could be:present in a Mark I boiling water reactor containment after a

. postulated accident would be limited to safe values. 'In response to Generic

. Letter 84-09,'CP&L has provided the design details of a modification to the;

- . Brunswick instrument air' system that would isolate the. air supply to pneumatic

-valves inside containment after a postulated loss of coolant accident (LOCA).

The only. pneumatic valves inside containment that are required to operate after a LOCA are the automatic depressurization' system -(ADS)' valves and the

a. torus to. reactor building vacuum breaker valves. The CP&L modification ~

. isolates the instrument air supply to containment-and lines up a pressurized

_ nitrogen supply for the ADS' and vacuum breaker valve operators. The.

switchover to the N7 supply occurs automatically on a LOCA signal, i.e., high

. ~drywell pressure coincident with low reactor pressure or low-low reactor water -

level.

By letter dated October 30, 1986,- the NRC issued a Safety Evaluation ~ relating to the acceptability of the N,, switchover modifications to the instrument air 3 system. -The staff provided a8ditional criteria to be applied to the N switchover system to assure that only nitrogen would be introduced int $ the containment after a postulated LOCA. Two of the criteria that would have to be met to-assure compliance with Generic Letter 84-09 involve the addition of

. Technical Specifications (TS) to 7 control the operability of the N2switchover system. That is, CP&L should provide:

.a. Testing and surveillance'TS for the essential N 2supply system, and

b. TS for the essential No supply system that limit operation of the plant on loss of redun8ancy and loss of the system.

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t. w 2- April 3, 1987 By letter dated December 19, 1986, CP&L responded to our Safety Evaluation and
subsequently requested a meeting to discuss the implementation of the requirements.for N2supply system TS.

Meeting Summary At the March 18, 1987 meeting with the staff, CPAL proposed that the N system and switchover function TS be included in an existing TS sectio $ supply rather than adding a new TS'section. Requirements for N,3 supply system pressure.

would be included in the existing vacuum breaker TS. That is, a decrease in Np pressure in either of two supply headers below an alarmed setpoint would require the vacuum breakers to be declared inoperable. At the pressure setpoint chosen, there would still'be sufficient nitrogen pressure.available to' operate the ADS and vacuum breaker valves for a predetermined' number of days with normal system leakage.

1 The staff advised CP&L that, while this might be an acceptable approach to.

ensuring nitrogen system availability,.TS would also be needed to ensure operability of the N7switchover valves and actuation logic. The staff also expressed concern that the current actuation signal that uses high drywell pressure coincident with low reactor pressure may be inadequate to assure air system isolation for small-break LOCAs and instrument air line breaks inside the drywell.

CP&L' agreed to submit TS for nitrogen system pressure and the nitrogen switchover function by March 27, 1987. Other proposals relative to N

- switchover actuation signal and design features to ensure. air isolatibn considering a single active failure in the isolation system will also be addressed.

Ernest D. Sylvester, Project Manager BWR Project Directorate #2 Division of BWR Licensing

Enclosure:

As stated cc w/ enclosure:

See next page p n

0FFICIAL RECORD COPY l DBL:PD#2 k DBL:PD#2 ESylvester:cb DMuller 4 /2-/87 A /1 /87

, t-a llEETING ATTENDEES NRC CP&L JKudrick SZinnerman PHearn SFloyd ESylvester RPoulk

2 Mr. E. E. Utley - Brunswick Steam Electric Plant Carolina Power & Light Company Units 1 and 2 cc:

Mr. P. W. Howe Mr. C. R. Dietz Vice President Plant General Manager Brunswick Nuclear Project Brunswick Nuclear Project Box 10429 Box 10429 Southpert, North Carolina 28461 Southport, North Carolina 28461 Thomas A. Baxter, Esquire Mr. H. A. Cole Shaw, Pittman. Potts & Trowbridge Special Deputy Attorney General 2300 N Street, N. W. State of North Carolina .

Washington, D. C. 20037 Post Office Box 629 Raleigh, North Carolina 27602 Mr. D. E. Mcllar Associate General Counsel Mr. Robert P. Gruber Carolina Pcwer & Light Company Executive Director Post Office Box 1551 Public Staff - NCUC Raleigh, North Carolina 27602 Post Office Box 29520 Raleigh, North Carolina 27626-Ob20 Mr. Christopher Chappell, Chairman Board of Ccmmissioners -

Post.0ffice Box 249 Bolivia, North Carolina 28422 Mrs. Chrys Baggett State Clearinghouse Budget and Management 116 West Jones Street Raleigh, North Carolina 27603 Resident Inspector U. S. Nuclear Regulatory Commission Star Route 1 Post Office Box 208 Southport, North Carolina 28461 -

Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 2900 Atlanta, Georgia 30303 Mr. Dayne H. Brown, Chief Radiation Protection Branch Division of Facility Services -

N. C. Department of Human Resources 701 Barbour Drive Raleigh, North Carolina 27603-2008

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