ML20032A016
| ML20032A016 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 09/09/1981 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | Jackie Jones CAROLINA POWER & LIGHT CO. |
| References | |
| NUDOCS 8110280155 | |
| Download: ML20032A016 (10) | |
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September 9,1981 Cb
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Docket Nos. 50-325 and 50-324 g
fir. J. A. Jones 00T l 6 JSadII
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Senior Executive Vice President u.a. axa...D 99eu Carolina Power & Light Company y
336 Fayetteville Street 4
p Raleigh, North Carolina 27602 d
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Dear fir. Jones:
By letter dated July 7,1980, we requerted that you propose Technical Specification changes for Brunswick Units 1 and 2 to provide surveil-lance requirements for scram discharge volume (SDV) vent and drain valves and LC0/ surveillance requirements for RPS and control rod block SDV limit switches.
Our consultant, Franklin Research Center (FRC), has reviewed your submittal in response to this letter and has identified the need for additional infomation. He have evaluated the FRC document and agree that this information is needed in order to complete our review.
Accordingly, please provide the additional inforration requested in the enclosure within forty-five (45) days of your receipt of this letter.
If you or your staff have any questions on this matter, please contact your project manager.
Sincerely, Thomas A. Ippolito, Chief Operating Reactors Branch #2 Division of Licensing g
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Enclosure:
Request j
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Mr. J. A. Js ies CC*
F.ichard E. Jones, Esquire Carolina Power & Light Company 336 Fayetteville Str'eet Raleigh, North Carolina 27602 George F. Trowbridge, Esquire Shaw, Pittman, Potts & Trowbridge 1800 M Street, N. W.
Washington, D. C.
20036 John J. Burney, Jr., Esquire Burney, Burney, Sperry & Barefoot 110 North Fifth Avenue Wilmington, North Carolina 28401 F.esident I:.spector U. S. Nuclear Regulatory Comm.ission P. O. Box 1057 Southport, North Carciina 28461 Southport - Brunswick County Library 109 K. Moore Street Southport, North Carclina 28461 "r. Charles R. Dietz Flant Manager F. D. Box 458 Southport, North Carolina. 2S461
t REQUEST FOR ADDITIONAL INFORMATION
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BWR SCRAM DISCHARGE VOLUME LONG-TERM MODIFICATIONS CAROLINA POWER & LIGHT COMPANY
!BRUNSWICKSTEAMELECTRICPLANTUNITS1AtiD2 l-1
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50-325, 50-324 l
NRC TAC NO.
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_ 0.Franklin Research Center A Division of The FrankJin Institute The Ben,anin Franidin Parkway. Phila.. Pa. 19103 (215)448 1000
BACKGROUND This Request for #.dditional Information (RFI) is t'he result.of an evaluation of information contained in a letter dated November 13, 1980 from Carclina Power & Light to the Nuclear Regulatory Commission (NRC) in response tc NRC's request for Technical Specifications changes regarding Brunswick i
Steam Electric Plant Units 1 and 2 surveillance requirements for scram discharge volume (SDV) vent and drain valves, and limiting cenditions for op'eration (If0)/ surveillance requirements for reactor protection system (RPS)
- and control rod block SDV limit switches. The evaluation was made in accordance with criteria contained in the Model Technical Specifications proposed by NRC staff and incorporated into the General Electric Standard
- The eva uat on revea el d three iter.s of l
i Technical Specifications.
concern to which incomplete responses were obtained.
Additional information related to these items of concern is needed before a final evaluation of the proposed Technical Specification changes' for -
Brunswick Steam Electric Plant Units 1 and 2 can be made.
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REQUESTED CHANGES IN TECHNICAL SPECIFICATIONS The changes in Technical Specifications involve surveillance requirements of the main components and instrumentation of the scram discharge volume.
They cover three areas of concern, as described below.
I.
Surveillance Recuirements for SDV Drain and Vent Valves The surveillance requirements of the Model Technical Specifications for
.SDV drain and vent'valvic arc.
"4.1.3.1.1 - The scram discharge volume drain and vent. valves shall be, demonstrated OPERABLE at least once per 31 days by:
Verifying each valve to be open*, and a.
b.. Cycling each valve at least one complete cycle of full travel.
"*These valves may be closed intermittently for testing under admini,strative controls."
Carolina Power & Light Company's response to the above surveillance; requirements for SDV drain and vent valves is given'in the subsequent parag r,aph:
" 4.1. 3.1.1 The scram discharge volume drain and vent valves shall be verified open at least once per 31 days.*
"*These valves may be closed intermittently for testing under administrative control."
l ITEM 1 CONCERN Carolina Power & Light Company's response in paragraph 4.1.3.1.1 should also contain the requirement. of the Model Technical Specificationn paragraph 4.1.3.1.1.b to cycle each valve at least one complete cycle of full travel at least once per 31 days..
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REQUEST
- 1. Provide a reference to the Technical Specification section for Brunswick Steam Electric Plant Units 1 and 2 where the requested change for surveillance requirements of the drain and vent valves is incorporated, or
- 2. Provide technical bases why the requested change is not applicable to Brunswick Steam Electric Plant Units 1 and 2.
II.
LCO/ Surveillance Recuirements for Reactor Protection System Scram Discharce Volume Limit Switches The required changes in the Technical Specifications with reference to
'LCO/ surveillance requirements for reactor protection system scram discharge volume limit switches are given in the NRC staf f's Model Technical Specifications as reproduced below..
"3.3.1 - As a minimum, the reactor protectio, system instrumentation
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channels shown in Table 3.3.1-1 shall be OPERAELE with the REACTOR PROIECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.
"4.3.1.1 - Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the f requencies shown in Table 4.3.1.1-1."
The required information from the tables referred to in the above paragraphs follows.
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_ A Dras.on of The Frennhn lasvame L
r Taole 3.3.1-1.
Reactor Protection System Instrumentation Applicable Minimum Operable Functional Operational Channels'Per Trip Unit Conditions System (a)
Action 8.
Scra;n Discharge Volume Water Level-High 1,2,5(h) 2 4
NOTATION :
(a) A channel may be placed in an inoperable status up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.
s (h) With any control rod withdrawn. Not applicable to control rods t
remove.4 per Specification 3.9.10.1 or 3.9.10.2.
In OPERATIONAL CONDITION 1 or 2, be in at least hor SHUTDOWN within Action 4:
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
In OPERATIONAL CONDITION 5, suspend all operations involving CORE ALTERATIONS
- and fully insert all insertable contrcl rods within one hour.
Table 3.3.1-2.
Reactor Protection System Response Times Functional Response Time Unit (Seconds) 8.
Scram Discharge Volume Water Level-High NA Table 4.3.1.1-1.
Reactor Protection System Instrumentation Su,rveillance Requirements Channel Operational Functional Channel Functional Channel Conditions in Which Unit Check Test Calibration Surveillance Recuired
- 8. Scram Discharge Volume Water Level-High NA M
R 1,2,5 M
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ITEM 2 CONCERN i
Referring to paragraph 4.3.1.1 and Table 4.3.1.1-1 of the Model Technical Specifications, the Technical Specifications for Brunswick Steam Electric Plant Units 1 and 2 should contain a similar paragraph and table or an equivalent paragraph stating t!.at each reactor protection system scram discharge volume water 1.evel-high instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL FUNCTIONAL TEST cnce per month and CHA! CIEL CALIBRATION operations each refuelling outage for the OPERATIONAL CCICITIONS 1, 2, and 5.
REQUEST
- 1..
Provide technical bases for the quarterly CHANNEL FUNCTIONAL TEST frequency required by the Brunswick Steam Electric Plant Units 1 and 2 Technical Specifications as opposed to the recommended monthly frequency.
III.
LCO/ Surveillance Recuirements for Control Rod Block Scram Discharge Volume Limit Switches Tne provisions of the Model Technical Specificatio$s in regard to LCO/ surveillance requirements for control rod block scram discharge volume limit switches are:
"3.3.6.
Tne control rod withdrawal block instrumentation channels shown in Table 3.3.6-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.6-2.
"4.3.6. 'Each of the above required co;1 trol rod withdrawal block trip systems and instrumentation channels, shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, 'CHA?.NEL FUNCTIONAL TEST and CHANNEL CALIBRATION operatiens for the OPERATIONAL cot 3DITIONS and at the f requencies shown in Table 4.3.6-1."
The information contained in the tables referred to in the above paragraphs follows.
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Control Rod Withdrawal Block Instrumentation 2
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Trip Channels Per Trip Operational Function Function Conditions
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Scram Trip Bypassed 1-1,2,5 *
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- With more than one control rod withdrawn. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.
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Action 62: With the number of OPERABLE channels less thAn required by the minimum OPERABLE channels per trip function' requirement, place the Inoperable channel in the tripped condition within one hour.
't Table 3.3.6-2.
Control Rod Withdrawal Block Instrumentation Setpoints Trio Function Trio Setooint Al
- $dLValue 5.
Scram Dis [:harge Volume 2
- a. Water Level-High 118 gallons 118 gallons
- b. Scram Trip Bypassed NA NA
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Table 4.3.6-1.
Control Fod Withdrawal Block' Instrumentation Surveillance '
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Trip Channel Functional Chanrel Conditions In Which Function Check Test Calibration Surveillance Recuired
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Bypassed NA M
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- As in Table 3.3.6-1.
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Referring to yhragrepn 3.3.6,and Table 3.3.6-2 of the Model Technical
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Specificatilons, the trip setpoint for" control rod block limit. switch SDV s
w&terQevel-high is spec,ified to be a sr.iall. volume.
The Technical I
Spec?fications foh.$runswick StearfElectrie: Plant Units 1 and 2 specify the trip setpoint of < 73 gallons.
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Since the setpoint in regard to t)b!ccotrol rod withdrawal block SDV i.,- ' water.Je't31-high is' greater than expected, provide technical bases for it..
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