ML20137M761

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Application for Amends to Licenses DPR-62 & DPR-71,revising Tech Specs to Correct Misspellings,Incorrect Referencing of Tables & to Make Technical Correction Re Fire Suppression Sys Pumps for Unit 1.Fee Paid
ML20137M761
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 09/06/1985
From: Cutter A
CAROLINA POWER & LIGHT CO.
To: Vassallo D
Office of Nuclear Reactor Regulation
Shared Package
ML20137M766 List:
References
NLS-85-068, NLS-85-68, NUDOCS 8509130322
Download: ML20137M761 (8)


Text

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4 CD&L Carolina Power & Light Company I

SEP 0 61985 SERIAL: NLS-85-068 s

Director of Nuclear Reactor Regulation s Attention: Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT CORRECTIONS TO TECHNICAL SPECIFICATIONS

Dear Mr. Vassallo:

SUMMARY

In accordance with the Code of Federal Regulations, Title to, Parts 50.90 and 2.101, Carolina Power & Light Company (CP&L) hereby requests revisions to the Technical Specifications (TS) for Brunswick Steam Electric Plant (BSEP), Unit Nos. I and 2. The proposed revisions involve administrative corrections to both BSEP-1 and BSEP-2 and a technical correction to BSEP-1.

The administrative corrections include misspellings, inadvertent omissions, mislabeling, incorrect referencing of TS Tables and sections, and deletion of footnotes.

The technical correction deals with the operation of the fire suppression system pumps.

The BWR/4 Standard TS and the BSEP-2 TS require operation of the fire suppression system pumps for at least 15 minutes whereas the BSEP-l TS requires operation of the pumps for at least 20 minutes. A revision to BSEP-1 TS is requested in order to provide consistency between BSEP-1, BSEP-2, and the BWR/4 Standard TS.

A detailed discussion of each proposed revision is provided in Enclosure 1.

SIGNIFICANT HAZARDS ANALYSIS The Company has reviewed this request and has determined that the proposed revisions do not increase the probability or consequences of an accident previously evaluated, or create the possibility of a new accident because there are no physical alterations of the plant configuration or changes to setpoints or operating parameters. The proposed administrative revisions merely correct typographical errors. Due to the administrative nature of these revisions, the margin of safety is not reduced.

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Mr. D. B. Vassallo Page 2 The Company has reviewed this request and has determined that revising the fire suppression pump operability time for BSEP-1 to be consistent with that referenced in the BSEP-2 and Standard TS does not increase the probability or consequences of an accident previously evaluated, or create the possibility of a new accident because there are no physical alterations of the plant configuration or changes to setpoints or operating parameters. The purpose of the surveillance requirements is to assure that the fire suppression pumps are operable. The operability can be verified as readily in 15 minutes as it can be in 20 minutes. Therefore, no significant reduction in a margin of safety is involved.

The Company has reviewed the request for the proposed administrative revisions and the prop not !) (osed involveminor non-significant a significant increase technical revisionorand in the probability determinedofthat consequences these revisions do an accident previously evaluated, or (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety. Therefore, the proposed revisions involves no significant hazards consideration.

ADMINISTRATIVE INFORMATION The proposed BSEP-1 and BSEP-2 TS pages are provided in Enclosure 2 and Enclosure 3, respectively. A summary list of revisions is included with each set of TS pages for your convemence.

Carolina Power & Light Company has evaluated this request in accordance with the provisions of 10 CFR 170.12 and determined that a license amendment application fee is required. A check for $150 is enclosed in Imyment of this fee.

Please refer any questions concerning this submittal to Mr. Sherwood R. Zimmerman at (919) 836-6242.

Yours very tr i

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. B. Cutter - Vice Prbsident Nuclear Engineering & Licensing DJK/ccc (1204SNP)

Enclosures (3) cc: Mr. Dayne H. Brown Dr. J. Nelson Grace (NRC-Ril)

Mr. M. Grotenhuis (NRC)

Mr. W. H. Ruland (NRC-BNP)

A. B. Cutter, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are officers, employees, contractors, and ag "

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ENCLOSURE 1 TO NLS-85-068 DISCUSSION OF PROPOSED REVISIONS TO BSEP-1 AND BSEP-2 TECHNICAL SPECIFICATIONS i

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BRUNSWICK UNIT 1 BSEP-1 TS 4.3.3.3 inadvertently states . . . all channels in each Emergency Core Cooling System function shown in Table 3.3.3-3 are tested at least once every N times 12 months . . . The BWR/4 Standard TS indicates that these channels are tested at least once every N times 18 months. BSEP-2 TS states that these channels are tested at least once every N times 18 months. During the process of BSEP-1 amendment changes, the 18 months was inadvertently changed to 12 months. This amendment corrects this typographical error by changing 12 months to 18 months.

BSEP-1 TS 4.3.3.3 indicates a footnote referencing a one-time only exemption allowed to extend the Emergency Core Cooling System response test time for items I and 2 of Table 3.3.3-3 to the completion of the Spring 1981 outage. Since this outage has been completed, there is no longer a need for this actnote to remain in the TS. This amendment removes the outdated footnote from tLe TS.

BSEP-1 Table 3.3.5.1-1 and 4.3.5.1-1 inadvet tently indicate the Triaxial Time-History Accelographs Instrument (ENV-XT-823-2) is Iccated in the Reacter Building at the 65 ft. level on the drywell. The instrument is actually Iceated in the Reactor Building at the +89 ft. 4 in. level on the drywell. This amdoent corrects this typographical error by changing the location of the imtrunmca from the 65 ft level to the +89 f t. 4 in. level.

BSEP-1 Table 3.3.5.6-1 inadvertently omitted the word deep" in front of bed demineralizer. This amendment corrects the typographica! error by changing bed demineralizer to deep bed demineralizer.

BSEP-1 TS 3.3.7 has a misspelled word. This amendment corr'ects the spelling of the word "their".

BSEP-l TS 3.4.1.1 " ACTION:" indicates a footnote referencing special action until March 15,1981. Since this date for special action has expired, there is no longer a need for this footnote to remain in the TS. This amendment removes the out-of-date footnote from the TS.

BSEP-1 TS 4.4.1.1.1 was inadvertently labeled TS 4.4.1.1. This amendment corrects the typographical error by changing the label 4.4.1.1 to 4.4.1.1.1.

BSEP-1 TS 4.4.1.1.2 was inadvertently labeled 4.4.1.2. This amendment corrects the typographical error by changing the label 4.4.1.2 to 4.4.1.1.2.

BSEP-1 TS Bases 3/4.6.1.6 inadvertently states . . . that the containrnent peak air temperature does not exceed the design temperature of 135*F during LOCA conditions . . . The drywell design temperature as listed in Table 5.2-1 of the FSAR 4

is 300*F. This amendment corrects the typographical error by changing 135'F to 300*F.

BSEP-1 TS 4.7.7.1.1.b inadvertently states ". . . the fire suppression water system shall be demonstrated OPERABLE at least once per 31 days on a STAGGEReiD TEST BASIS by starting each pump and operating it for dt test 20 minutes." The BWR/4 standard TS indicates that the pumps should be operatAd for at least 15 minutes. In addition, the BSEP-2 TS currently requires operation of the fire suppression system (1204sNP/ccc)

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pumps for 15 minutes. The proposed revision changes the BSEP-1 TS to require 15 minute operation, thus providing consistency between BSEP-1, BSEP-2, and BWR/4 Standard TS.

BRUNSWICK 1; NIT 2 BSEP-2 TS 3.1.3.2, " APPLICABILITY" inadvertently omitted " OPERATIONAL" in front of CONDITIONS I and 2. This amendment corrects the typographical error by changing CONDITIONS 1 and 2 to OPERATIONAL CONDITIONS I and 2.

BSEP-2 TS 4.1.3.2 was inadvertently labeled as TS 4.1.2.1. This amendment corrects the typographical erroc by changing the label 4.1.2.1 to 4.1.3.2.

BSEP-2 TS 3.3.4 inadvertently indicates that Control Rod Withdrawal Block Instrumentation Setpoints are listed in Table 3.3.4-1. Table 3.3.4-1 lists the Control Rod Withdrawal Block Instrumentation not the setpoints. The setpoints are listed in Table 3.3.4-2. This amendment corrects the typographical error by changing the reference to the Trip Setpoint from Table 3.3.4-1 to Table 3.3.4-2.

BSEP-2 Tables 3.3.5.1-1 and 4.3.5.1-1 inadvertentfy indicate the Triaxial Time-History Accelographs Instrument (ENV-XT-823-2) is located in the Reactor Building at the 65 ft. level on the drywell. The instrument is actually located in the Reactor Building at the +89 f t. 4 in. level on the drywell. This amendment corrects this typographical error by changing the location of the instrument from the 65 f t, level to the +89 ft. 4 in level.

BSEP-2 Tables 3.3.5.1-1 and 4.3.5.1-1 inadvertently indicates the Triaxial Peak Shock Recorders Instrument (ENV-XRH-823-3) is located in the Reactor Building at the +17 ft. level. Instrument ENV-XRH-823-3 is actually located in the Reactor Building at +1l7 ft. level. This amendment corrects the typographical error by changing the location from +17 ft. to +117 ft.

BSEP-2 Table 3.3.5.6-1 inadvertently omitted the word " deep" in front of bed demineralizer. This amendment corrects the typographical error by changin;; bed demineralizer to deep bed demineralizer.

BSEP-2 TS 4.3.6.1.2 was inadvertently labeled 4.3.6. 2. This amendment corrects the typographical error by changing 4.3.6. 2 to 4.3.6.1.2.

BSEP-2 TS 4.4.1.1.1 was inadvertently labeled TS 4.4.1.1. This amendment corrects the typographical error bv changing the label 4.4.1.1 to 4.4.1.1.1.

BSEP-2 TS 4.4.1.1.2 was inadvertently labeled 4.4.1.2. This amendment corrects the typographical error by changing the label 4.4.1.2 to 4.4.1.1.2.

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BSEP-2 TS Bases 3/4.6.1.6 inadvertently states . . . that the containment peak air

- temperature does not exceed the design temperature of 135*F during LOCA conditions . . . The drywell design temperature as listed in Table 5.2-1 of the FSAR is 300*F. This amendment corrects this typographical error by changing 135'F to 300 F.

BSEP-2 Table 3.7.7.4-1 inadvertently indicates that the Fire Hose Stations in the Control Building at the 23 ft. and 49 ft. elevations are on Hose Rack #1-CB-1 and

  1. 1-CB-2, respectively. The Hose Rack numbers should read #2-CB-1 and #2-CB-2.

This amendment corrects .these typographical errors by changing the Hose Rack numbers from #1-CB-1 and #1-CB-2 to #2-CB-1 and #2-CB-2, respectively.

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r-ENCLOSURE 2 TO NLS-85-068 PROPOSED BRUNSWICK UNIT 1 TECHNICAL SPECIFICATIONS PAGES (84TSB51) i l

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SUMMARY

LIST OF REVISIONS BRUNSWICK-1 l

Page Description of Change 3/4 3-30 Item 4.3.3.3 - Revise to change . . . once every N times 12 months . . . to . . . once every N times 18 months . . .

Item 4.3.3.3 ' Delete

  • footnote 3/4 3-45 Table 3.3.5.1 Revise 1.a. to change 65' to +89' 4" i Table 4.3.5.1 Revise 1.a. to change +65' to +89' 4" 3/4 3-46 3/4 3-56 Table 3.3.5.6 Revise to change bed demineralizer to deep bed demineralizer
3/4 3-82 Item 3.3.7 - Revise to change spelling of "ther" to "their" 3/44-1 Item 3.4.1.1 " ACTION
" - Delete *
  • footnote Item 4.4.1.1.1 - Revise to change 4.4.1.1 to 4.4.1.1.1 Item 4.4.1.l.2 - Revise to change 4.4.1.2 to 4.4.1.1.2 B3/4 6-2 Item 3/4.6.1.6 - Revise to change 135*F to 300 F 1

3/4 7-18 Item 4.7.7.1.1.b - Revise to change 20 minutes t'o 15 minutes i

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