ML18031B306

LER 87-006-00:on 870302,discovered That Routine Flow Rate Surveillance on Control Room Emergency Ventilation Train B Performed Incorrectly on 870301.Caused by Personnel Error. Correct Zeroing Procedure clarified.W/870428 Ltr

ML18031B306
Person / Time
Site:	Browns Ferry
Issue date:	04/28/1987
From:	Gordon A, Robert Lewis TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-87-006-01, LER-87-6-1, NUDOCS 8705050377
Download: ML18031B306 (10)

Text

REGULATORY IY'3Ri')ATION DISTRIBUTION: Y. TF"'R IDB>

ACCESSION NBR: 8/05050377 DQ". DATE: $ 7/Ow/28 NQTARJZEJ>; NO DOCS,ET FACIL: 50-259 Brains Fevv g Nucleav Pouc- S+ation> Unit J Tenness"e ~

Nhl'lE AUTHOR APF I!.. I A l'IO 0500025'UTH.

GORDON, A. W fennessee Valley Au+hov itq LEWIS> R. ) . le>>nessee Valle<<> Authority RECIP. NAME RECIPII;N1 AFFIL IATIQA'UB JEC1: LER 87-006-00: on 870302> Ciscovev ed that routine flour rate surveillance an contv ol room emeroencg venti Jatian tv ain B pev fov'med incov v ectly night before. Thv o+tl". damper may not have been set to delivev design basis floe. 8/870428 ltv.

DISTRIBUTION CODF: IE22D COPIES RECEiVED: LTR ENCL BI ZE:

TITLE: 5p. 73 Licensee Event Repov t (LFR) Incident Rpt. ~ <<tc.

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NRC Form 3dd U.S. NUCLEAR REGULATORY COMMISSION ID 83)

APPROVED OMB NO. 3150410a LICENSEE EVENT REPORT (LER) EXPIRES; 8/31/88 FACILITY NAME (1) DOCKET NUMBER (2) PA E 3 Browns Ferr Unit 1 0 5 0 0 p 2 5 9 1 OF 0 3

'5+ioper Flow Testing of Control Room Emergency Ventilation Fans Leads to Prohibited Condition EVENT DATE IS> LER NUMBER (5) REPOAT DATE (7) OTHER FACILITIES INVOLVED Id)

MONTH DAY YEAR YEAR .:~; SEOUENTIAL )C'c IIEVicrON MONTH OAY YEAR FACILITYNAMES OOCKFT NUMBER(BI NUMDEII '8%i NUMBER Browns Ferr Unit 2 o s o o o 2 6 0 0 3 02 87 8 7 0 0 6 0 0 0428 8 7 Browns Ferr THIS REPORT IS SUBMITTED PUASUAN'7 T 0 THE REQUIREMENTS OF 10 CFR II: (Cheart one or more Unit 3 oi the ioiiowrnfi (11) o s o o o 2 9 6 OPERATINO MODE (DI 20.802(8) 20.c05(c) 50,73(el(2 I(iv) 73.71(DI POWER 20.C05(e illI (i) 50.38(cl(1) 50.73( ~ l(2)(vl 73.7 1(c)

LE v E L 0 0 20.C05(a ) (I I (ll) d0.38(c)(2) 50.73( ~ )(2)(vd) OTHER iSoeciry in AOttrect oe/ow enrrin year, NRc form 20.a05(a I (1)(iiiI X 50.73lal l2) (i) 50.73(el(2)(viii)IAI 366AI 20A05(a) Ill(lv) X 50.73(e) (2) lil) 50,73 ( ~ ) (2 I (alii) I 8 I l~@j%<ir7)v&kh;: 20.405(e) llllvl 50.73(e)(2) Iiil) S0.73( ~ )(2)lx)

LICENSEE CONTACT FOA THIS LER (12I NAME TELEPHONE NVMBER AREA CODE Alan W. Gordon En ineer, Plant 0 erations Review Staff COMPLETE ONE LINE FOA EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) 20 5729 -25 7 CAUSE SYSTEM COMPONENT MANUFAC.

TVAER REPORTABLE TO NPRDS

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SYSTEM COMPONENT MANUFAC.

TURER EPOATABLE TO NPRDS

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5L'Sg.iPih~va2)F+r.'i%4rS 1UPPLEMENTAL REPOA'1 EXPECTED (I ~ ) MONTH DAY YEAR EXPECTED SUBMISSION DATE I'IS)

YES (ii yer, complete EXPECTED SUSAIISSION DATE) X rto ABSTRACT (Limit to 1600 epecet, I 5, epproaimereiy AINen eincie.apace typewritren iirni lid)

On March 2, 1987, it was discovered that a routine flow rate surveillance on control room emergency ventilation (CREV) train B had been performed incorrectly the night before. The surveillance had made use of new flow test instrumentation for the fiest time, and the test personnel had not properly zeroed the instrument. Engineers, reviewing the test data, noted that a throttle damper adjustment had been made to meet the flow acceptance criteria.

Retesting with a properly zeroed instrument they found the flow to be somewhat below the design basis requirements. The throttle dampee may not have been set to deliver the design basis flow since initial system installation, Operations declared CREV B inoperable when informed at 1620 hours0.0188 days <br />0.45 hours <br />0.00268 weeks <br />6.1641e-4 months <br />. The flow was immediately measured and correctly set. However, on the morning of March 2, 1987, when CREV A was believed operable, foue new fuel bundles were moved to the refuel floor and placed in the unit 1 spent fuel pool. The unit 1 reactor vessel and drywell heads were in place, but, interpreting this fuel movement as a refueling operation, technical specifications relative to CREV operability were not satisfied.

Numeeous tests were subsequently performed using a wide vaeiety of flow measurement devices in an effort to establish the best method for the particular configueation. Confusion regarding the correct zeroing procedure has been resolved, and the personnel involved have been instructed on the correct use of the instrument.

8705050377 870028 NRC Form 3dd PDR ADOCK 05000259 ID 83i S PDR

NRC FoNR 366A U.S. NUCLEAR REGULATORY COMMISSION (94)3)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPAOVEO OMB NO, 3160M)04 EXPIRES: 6/3)/SB FACILITY NAME (Il DOCKET NUMBER (2) LER NUMBER (6) PACE (3)

YEAR SSOUENTIAL .:.jC REVlSION

?~$ NUMBER NUMSER Browns Ferr Unit 1 o s o o o 259 8 7 0 0 6 00 02 OF 0 3 TEXT /i/met 4/>>OO /4 nqoOod, F44 Oddity'ooo////IC Fono 36649/ (IT)

Units 1, 2, and 3 were in refueling outages and completely defueled during the time frame of the events described below.

A revised surveillance test was performed for the first time on the control emergency ventilation (CREV) (EIIS code VI) train B on March 1, 1987. 'oom The new procedure made use of more modern flow instrumentation.. A pitot tube and micromanometer were used instead of the standard rotating vane instrument to measure CREV system flow. At 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br /> the test personnel turned CREV B over to operations. Following a ten hour test run, operations declared CREV B operable at 0600 on March 2, 1987. At 0620 CREV train A was tagged out of service for inspection.

On March 2,1987, it was noted by engineers reviewing the test data that the throttle damper at the train discharge had been opened slightly to meet the flow acceptance criteria. It was decided to determine if the original damper position would have been adequate for meeting the design basis flow rate of 500 cfm + 10 percent. However, with CREV A out of service, operations would not permit the throttle damper on CREV B to be readjusted. Flow measurements were performed on CREV B without moving the damper in order to compare the measurements of the vane anemometer to those of the pitot tube/micromanometer method. When initial readings (395 cfm) did not match the readings of the previous day (474 cfm),discussions with test personnel revealed the micromanometer had not been properly zeroed when used for flow measurements on March 1, 1987, This information was brought to the attention of operationspersonnel at 1620, and , as a conservative measure, CREV B was declared inoperable, The throttle damper may not have been set to deliver the true design basis flow since initial system installation. This could not be ascertained.

The CREV B flow was measured and set with a properly zeroed manometer immediately after operations was notified. However, on the morning of March 2, 1987, when CREV B was believed to be operable, four new fuel bundles were moved to the refuel floor and placed in the unit 1 spent fuel pool. BFN technical specification 3.7.E.4 requires that, with both CREV trains inoperable refueling operations cease within two hours. The unit 1 reactor vessel and drywell heads were in place. However, interpreting the handling of new fuel in the vicinity of irradiated fuel in the storage racks as a refueling operation, this requirement was not met.

Earlier test methodology was never regarded as being deficient. ANSI N510 (1980) lists the rotating vane anemometer as acceptable test apparatus.. The surveillance procedure was revised to use a pitot tube traverse and micromanometer in lieu of the rotating vane instrument following an NRC inspection concern. The vane instrument was used at various points on the CREV B exhaust grill because no straight run of duct exists for this train, and an ideal pitot tube traverse could not be made. Previous test data showed good accuracy in the velocity ranges used and consistent results.

Numerous tests were subsequently performed using a wide variety of flow measurement devices, in an effort to establish the best method for the installation configuration. Confusion NRC FORM 366A (94)3)

NRC Form 388A U.S. NUCLEAR REOULATORY COMMISSION (843)

LICENSEE EVENT REPORT ILER) TEXT CONTINUATION APPROVEO OMS NO. 3I50-0)04 EXPIRES: 8/31/88 FACILITY NAME (I) DOCKET NUMBER (2) PACE (3)

LER NUMBER (8)

YEAR SEOUENTIAL ~N(F REVISION f

NUMB 4 od NUMSf 4 Browns Ferr Unit 1 TEXT /// moro spoof /s roqo/rod, Irso oddR/ono///RC irorrn 3854 3/ (17) 05000259 8 7 0 0 6 0 0 03 QF 0 3 regarding the correct zeroing procedure for the micromanometer has been resolved, and the personnel involved have been instructed on the correct use of the instrument. Research has revealed several CREV installation discrepancies, none of which are believed to affect system operability or testability. Further CREV system studies are continuing.

The CREV system is designed to enhance control room habitability in the event of a loss of coolant or fuel handling accident resulting in a ground level radioactive release. The two trains are 100 percent redundant and either is capable of maintaining positive pressure in the control rooms. With CREV B adjusted to deliver a substandard flow, control room pressurization would be adversely affected, while filtration efficiency would be increased.

Res onsible Plant Section - NA Previous Similar Events None NRC FORM 35SA (983)

TENNFSSEL. VALLEY AUTHORITY Browns Ferry Nuclear Plant P.O. Box 2000 Decatur, Alabama 35602 April 28,1987 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Dear Sir:

TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT UNIT 1 DOCKET NO. 50-259 - FACILITY OPERATING LICENSE DPR REPORTABLE OCCURRENCE REPORT BFRO-50-259/87006 The enclosed report provides details concerning the improper control room emergency ventilation (CREV) flow testing which led to technical specification requirements not being satisfied. Problems with CREV testing were initially realized on March 2, 1987. However, since all of the facts were not known, reportability was delayed pending further investigation and formulation of data.

Test methodology comparisons, system configuration studies, and technical specification interpretations were needed to properly assess the plant condition relative to past, CREV operability and to verify the applicable reporting categories, System studies are continuing. A 30-day extension for the submittal of this LER was coordinated with Art Johnson of the Region Ii'. staff on April 2, 1987. This report is submitted in accordance with 10 CFR 50,73 (a)(2)(i) and 10 CFR 50.73 (a)(2)(ii).

Very truly yours, TENNESSEE VALLEY AUTHORITY

/

Robert L. ew s Plant Manager Browns Ferry Nuclear Plant Enclosures cc (Enclosures):

Regional Administration INPO Records Center U.S. Nuclear Regulatory Commission Suite 1500 Office of Inspection and Enforcement 1100 Circle 75 Parkway Region II Atlanta, Georgia 30339 101 Marietta Street, Suite 2900 Atlanta, Georgia 30303 NRC Resident Inspector, Browns Ferry Nuclear Plant An Equal Opportunity Employer

U. S. Nuclear Regulatory Commission April 28,1987 RIMS, MR 4N 72A-C (w/10CFR21, Form BF-19, and Form BF-90)

R. L. Gridley, LP SN 157B-C (Attn: McCloud, Shell) T. G. Chapman, Browns Ferry W. H. Hannum, BR 1N 77B-C R. G. Jones, Browns Ferry R. J. Johnson, POTC (Attn: N. S. Catron) G. G. Turner, Browns Ferry G. W. Killian, LP 4N 53A-C (Attn: L. S. Clardy)

M. E. Rivers, 201 SPB-K S. R. Maehr, Browns Ferry J. L. McAnally, LP 5S 83E-C M. J. May, Browns Ferry R. K. Sieberling, 716 C EB-C H. P. Pomrehn, Browns Ferry C. W. Beasley, Browns Ferry P. P. Carier, Browns Ferry W. C, Thomison, Browns Ferry This was prepared principally by Alan W. Gordon.

DISTR I ION EDocket le Projects Rdg.

~

CJamerson DOCKET NO(S) . 50-259/260/296 Hr. S. A. Mhite. Manager of Nuclear Power Tennessee Valley Authority 6N 38A Lookout Place 1101 Hark'et Street Cbhttanooga, TN 37402-2801

SUBJECT:

BROMNS FERRY NUCLEAR PLANT, UNITS I, 2 and 8 The following documents concerning our review of the subject facility are transmitted for your information.

Notice of Receipt of Application, dated Draft/Final Environmental Statement, dated Notice of Availability of Draft/Final Environmental Statement, dated Safety Evaluation Report, or Supplement No. dated Environmental Assessment and Finding of No Significant Impact, dated Notice of Consideration of Issuance of Facility Operating License or Amendment to Faci 1 i ty Operating Li cense, dated QX di ddd d

• d<<dd d, Bi-Meekly Notice; Applications and Amendments to Operating Licenses Involving No d dd~i8 ldddd d d]

Exemption, dated Construction Permit No. CPPR-Facility Operating License No.,

Order Extending Construction Completion Date, dated

, Amendment No.

Amendment No.

dated dated Monthly Operating Report for transmitted by letter dated Annual/Semi-Annual Report-transmitted by letter dated OTHER: Expiration date for hearing requests and comments: Hay 8, 1987.

Office of Nuclear Reactor Regulation

Enclosures:

Division of TVA Projects, OSP As stated CC:

OFFICE) OSP

~ ~~~~~~~~ ~ ~ ~ ~ ~ ~

'URNAME( 'Jamer n:

DATE III 04/25/

~~ ~ ~~ ~~ ~~~~~ ~ ~~ ~~~ ~ ~ ~

NRC FORM 318 (10/801NRCM 0240 OFFICIAL RECORD COPY

0 l

4 L"

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Mr. S. A. White Browns Ferry Nuclear Plant Tennessee Valley Authority Units 1, 2, and 3 CC:

General Counsel Resident Inspector/Browns Ferry Np Tennessee Valley Authority U.S. Nuclear Regulatory Commission 400 Commerce Avenue Route 2, Box 311 E 11B 330 Athens, Alabama 35611 Knoxville, Tennessee 37902 Mr. R. W. Cantrell Mr. Richard King ATTN: D. L. Williams c/o U.S. GAO Tennessee Valley'uthority 1111 North Shore 400 West Summit Hill Drive, W12 A12 Suite 225, Box 194 Knoxville, Tennessee 37902 Knoxville, Tennessee 37919 Mr. R. L. Gridley Tennessee Valley Authority 5N 157B Lookout Place Chattanooaa, Tennessee 37402-2801 Mr. M. J. May Tennessee Valley Authority Browns Ferry Nuclear Pla'nt P.O. Box 2000 Decatur, Alabama 35602 Mr. H. P. Pomrehn Tennessee Valley Authority Browns Ferry Nuclear Plant P.O. Box 2000

'Decatur, Alabama 35602 Chairman, Limestone County Commission P.O. Box 188 Athens, Alabama 35611 Claude Earl Fox, M.D.

State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36130 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W.

Atlanta, Georgia 30323 Mr. Steven Roessler U. S. Nuclear Regulatory Commission Reactor Training Center Osborne Office Center, Suite 200 Chattanooga, Tennessee 37411

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