ML20215B358

Informs Augmented Insp Team (AIT) of Activities During Jan 1987 in Order to Conclude AIT Insp & Issuance of Insp Rept. Insp Rept Based on 861217 Draft Executive Summary Requested by 870109.AIT Will Reconvene During Wk of 870112

ML20215B358
Person / Time
Site:	Surry
Issue date:	12/29/1986
From:	Panciera V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20215B065	List: ML20215B064 ML20215B135 ML20215B179 ML20215B280 ML20215B358 ML20215B402 ML20215B435 ML20215B540 ML20215B592 ML20215B624
References
FOIA-87-20 NUDOCS 8706170302
Download: ML20215B358 (9)

Text

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UNITED STATES

[ gas a:Gg*'o NUCLE AR REGULATORY cOMMisslON d' ~ ' '

R E GION 11 h '/2 101 MARIETT A ST RE ET, N W,

, y ATL ANTA GEORGI A 30323

%; s.s je Decerter 29, 1986

• ...a MEMORANDUM FOR: Augmented Inspection Team (AIT) Members - Surry Event of December 9, 1986 FROM: Vincent W. Panciera, AIT Leader

SUBJECT:

AIT ACTIVITIES The purpose of this memorandum is to inform the AIT of activities during the month of January in order to conclude the AIT inspection and issue the inspection report.

The draft executive summary which was issued on December 17 should be considered as an expanded outline in developing the inspection report. The same writing assignments should be followed in developing the inspection report as was done in developing the executive summary. Please submit your preliminary drafts to mebynoon,JanuaryJ.

I intend to reconvene the AIT _the week of January 12. At that time you should be prepared to inspect those areas which require further work as identified by your preliminary drafts. The licensee will present the conclusions of his review during the week of January 12. It is my intention to conduct an exit interview late that same week. At that time you should have completed your inspection and should be prepared to state your inspection findings and conclusions. The final drafts of your assigned sections of the inspection report should be turned in to me by January 16, 1987. I intend to issue the inspection report on January 23, 1987.

If you have additional questions concerning the planned activities of the Surry AIT, please contact me. i yVi@ncent W. a~au/ Panciera Distribution - AIT Members -

T. Peebles, DRP J. Caldwell, North Anna Senior Nsident W. Holland, Surry Senior Resident B. Crowley, DRS

\ W. Cooper, DRSS J. Gilliland, DRPA

% P. Taylor, DE M. Caruso. NRR cc: L. Shao, NRR G. Holahan, NRR A. Gibson, DRS R. Walker, DRP P. Stohr, DRSS

k. M: B?S F0ZA !?-'*

F. Cantrell, DRP gjg 8706170302 870611 PDR FDIA ZWELLING87-20 PDR

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VIII.

FACTORS WHICH POTENTIALLY COMPLICATED RESPONSE TO THE INCIDENT A. Security e

The pipe rupture resulted in water entering the cardreader located i outside Vital Battery Room 2B, Unit 2 Turbine Building Basement.

The water intrusion caused the Security System data line to

'become inoperable. The inoperable data line prevented access to areas via the cardreader system. Roving security officers immediately were dispatched to provide access. Exit from these areas could be accomplished by using emergency exit devices.

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,y The*.etcessive 'CO2 'discharg'e 1:i th eableltiray roomaVressYt'edlin'thk' Security radio repeaters becoming temporarily degraded. These repeaters provide for clearer radio communications by broadcasting .

amplified signals through the plant. With the degradation of the repeaters, direct communications between portable hand sets was used. The need to repeat a transmission or relocate to establish effective communication may have complicated response to the incident.

However, needed communication was accomplished using radios or the station gai-tronics system.

B.

Fire Protection System Actuation and Main Control Room Habitability Within a few minutes of the pipe rupture, the automatic Halon fire protection system actuated followed by a similar actuation of an automatic CO 2 fire pr tection system. The Halon system protects the Unit 1 and 2 Emergency Switchgear rooms located on the level immediately below the Main Control Room (MCR) area. The CO t 2

i system protects the Unit 1 and 2 Cable Tray rooms located on the level  ;

.immediately above the MCR area. In addition, 62 Unit 2 Turbine Build- i ing fire protection sprinkler heads discharged. Two of these sprinkler i VIII-l

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heads were located outside the Unit 2 Cable Tray rooms. Within approx-imately ten minutes, Ope.ations and Loss Prevention personnel veri-fled the areas had been evacuated and started ventilating them.

Yhe discharge of the Halon system resulted in undesirable in-leakage of Halon into the MCR through floor penetrations in the Unit 1 Computer Room and throvgh the Control Room Emergency air bottle discharge piping.

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The CO 2 818 penotrated the MCR area when the door to tua MCR Annex (MCRA) from the Unit 2 Turbine building was blocked open to facilitate per.1onnel movement into the MCRA and accommodate recovery activities in J . :. , * . , . ; , e. .. .ithe *Mit?.2.' tsrbine Su(1<iing..hillway'.~ ' %e d'oor to"the'NCR froai $b[)(CRA. 'O was also open with a security watch posted in accordance with normal (procedurefollowingareactortrip.

When the Halon vse observed in the MCR and MCR personnel reported some physical ditcomfort, the Control Room Emergency Supply Fans (1-VS-F-41 ated 2-VS-F-41) were started, restoring the air quality in the MCR area. Prior to starting these fans, the people in the MCR and MCRA reported varying degrees and combinations of ef fects including shortness of breath, dizziness, and nausea. These symptoms are primar-ily attributed to the CO since 2 they were reported in the MCRA and on the Unit 2 side of the MCR near the door to the NCRA. Operators on the Unit 1 side of the MCR, where the haze from the Halon in-leakage was reported, did not experience effects that hampered their ability to operate.

The Halon and CO2 in the MCR area did not adversely affect operator actions. Bottled air systems were available and their utilization was

. ev.alu a t e d .

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In addition to the affects on MCR habitability, station activities l i {

g. were'potentially impacted bye.

1.. hpproximately one inch of water in Unit 2 Cable Tray room 1 i

<7 i around floor penetratieas, allowing water to drip from the

'MCR seiling behind the Unit 2 vertical control board.

2. The CO 2 discharge in the Unit

• Cable Tray Room temp-orarily disabled the repeater for the Security frequency. j (hand sets were still functional). l

3. Undes'.vab?e in-leakage of CO .in an Instrument Shop area 4

2 and hallway below Mechanical Equipment Space No. 1. 1

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C0j in 'the sta[rw611 behind the 11CR.

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The loss of the entire CO ysystem when the main CO 2 st rage tank emptied as a result of excessive discharges to the Cable

, Tray Rooms.

Plant personnel responded well to both the accident and the resulting effects of the fire protection system actuations. Fire watches were posted immediately in the Unit 2 Turbine Building, Cable Tray rooms, Cable Vaults,': Emergency Diesel Cenerator rooms, and Emergency Switch-  ;

gear rooms, C. Communication Difficulties i i

The Nuclear Regulatory Commission Emergency Notification System (ENS)  ;

i telephone in the Control Room had some background noise. When '

communicatiens was shifted to the ENS telephone in the Technical Support Center (TSC) background noise increased. Contact was established and maintained using a commercial line. The ENS telephones have since

, been checked and found to be acceptable, d

VIII-3 1

,1 N. etoisse MEMORANDUM l

70 Distribution Insarvice Inspection FROM L. N. Hart: Dececber 31, 1986 NORTH ANNA UNIT 1 SECONDARY INSPECTION DATA

SUMMARY

Attached is a suasnary of the Unit 1 secondary inspections performed on 12/26/86. The final data set will be available by January 5, 1987.

Dist: W. L. Stewart J. L. Wilson E. W. Harrell G. E. Kane E. R. Smith, Jr.

J. A. Stall R. W. Calder J. E. Vrontevic H. L. Travis i

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NOP.TH ANNA UNIT 1 SECONDAM INSPECTION DATA SUW.ARY The following is a summary of the North Anns Unit I secondary piping j inspections performed on 12/26/86. This summary is based on raw data i and not f*.nal NDE reports. Minor changes may be identified once the final NDE reports are issued. E&C will be issuing a tSchnical report addressir4 the entire inspection effort.

'A' Feedwater Pucp Suction Line 7etet number of points inspected - 289 Total number with values less than nominal - 11 1 Nominal i:41ckt.ess .562 in.

Lowest value .543 i

% deviation - 3.4% i

'S' Feedwater Pump Suction Line i Total number of points inspected - 273 Total number with values less than nominal - 24 {

i Nominal thickness .562 in. {

Lowest value .530 l

% deviation - 5.7% l

'C' Feedwater Pump Suction Line j

Total number of pointa inspected - 284 Total number with values less than nominal - 32 ,

Nominal thicknest - .562 in, f

Low at value .534

% deviation - 5.0% l j

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'A' HP Heater Drain Pump Discharge Line k

Total number of points inspected - 381 {

Total number with values less than nominal - 19 .

Nominal thickness (10") .365 in.  ;

Lowest value .340 l

% deviation - 6.A%

Nominni thickness (6") .280 Lowest value .238 j

% deviation - 15.0%

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'B' HP Heater Drain Pump Discharge Line i I

Total number of points inspected - 384 Total number with values less than nominal - 32 Nominal thickness (10") .365 in.

Lowest value .332

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% deviation - 9.0% i Nominal thicknese (6") .280 I Lowest value .242

% deviation - 13.6% {

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'C' KP Esater Drain Pump Discharge Lina  !

Total number of points inspected - 381 Total number with values less than nominal - 25 Nominal thickness (10") .365 in.

Lowest value .340

% deviation - 6.9%

Nominal thickness (6") .280 Lowest value .271

% deviation - 3.2% t i

KP Hester Drain Line-to-rW Header Weldolets I Total number of points inspected - 1316 Total number with values less than nominal - 76 Nominal thickness (header) .688 in.

Lowest value .660

% deviation - 4.1%

Nominal thickness (drain line) .365 in.

Lowest value .345

% deviation - 5.5%  !

FW Header-to Pump Suction Tee's Total number of points inspected - 1544 Total number with values less than nominal - 148 Nominal thickness (header) .688 in. .

Lowest value .634

% deviation - 7.8%

Nominal thickness (suction piping) .562 in.

Lowest value .517

% deviation - 8.0%  !

FW Header End Cap Total number of points inspected - 42 Totsi number with values less than nominal - 0 Nominal thickness .688 in.

Lowest value .729

% deviation - + 6.0%

_ TOTAL - Number of points inspected - 4.894 i Number with values less than nominal - 367

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Notes: 1. Percent deviation is deviation from nominal to lowest value. ]

2. Inner and outer radius scans are counted as one j l

inspection point each.

3. Ses11er pipe nominal thickness is assumed for reducing j elbows and reducers.  ;

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QV 71RCINIA POWER /NRC KEETINC January 12, 1987

SUBJECT:

December 9, 1986 REACTOR TRIP AND FEEDPUNP SUCTION LINE PAILURE NAME AFFILIATION W. L. Stewart Virginia Power H. L. Miller Virginia Power R. F. Saunders Virginia Power J. M. McAvoy Virginia Power R. W. Calder Virginia Power R. J. Hardwick Virginia Power D. L. Benson Virginia Power J. Hoperfeld U. S. NRC A. Taboada U. S. NRC L. Engle U. S. NRC D. Terao U. S. NRC/NRR J. Nelson Crace U. S. NRC F. S. Cantrell, Jr. U. S. NRC V. W. Panciera U. S. NRC L. S. Rubenstein U. S. NRC C. P. Patel U. S. NRC W. E. Holland U. S. NRC J. L. Caldwell U. S. NRC R. J..Bosnak U. S. NRC

' Ernest B. Branch Sargent & Lundy Mark A. Carnso U. S. NRC E. J. Sullivan U. S. NRC William T. Cooper, Jr. U. S. NRC J. T. Rhodes Virginia Power C. L. Pannell Virginia Power  !

Ceorge Hudgins Virginia Power C. M. Jarvis Virginia Power W. F. Stephens Virginia SCC M. Tahamtani Virginia SCC D. S. Cruden Virginia Power J. M. Davis Virginia Power J. L. Perkins Virginia Power Nancy E. Clark Virginia Power John W. Waddill Virginia Power Michael T. Sedlark Technical Enterprises, Inc.  ;

Jim Lynch Daily Press W. J. Ross NRC - Region II E. W. Throckmorton Virginia Power H. T. Sink Virginia Power John Ahladas Virginia Power l

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,. u f l Virginia Power /NRC Meeting ,

January- 12, 1987 1 NAME AFFILIATION l

Edward A. Harper, Jr. Virginia Power W. Timothy Lough State Corporation Commission P. A. Taylor - NRC Region'II P. M. Madden NRC Region II F. R. Ellis Virginia Power Pat Scales UPI

' Bob Ceshe Virginian Pilot Joe Gilliland NRC Public Affairs .

J. F. Deucher U. S. Dept. of Energy 1 T. A. Peebles U. S. NRC -)

J. D. Ennis U. S. NRC - Region II .

l R. W. Cross Virginia Power - SPS W. R. Benthall Virginia Power - SPS

. Jim Mcdonald Virginia Power D. S. Firefroch News Leader

• Cregory Brown Stone and Webster Engr.

Carl Baab Virginia Power Michael 0'Hara Virginia Power j Tom Sweeney Virginia Power Judith Kator Citizen Action Safe Environment Michael Specter Washington Post C. E. Kube, Jr. Nuclear Operations - Virginia Power C. R. Silcox Surry - Virginia Power B. J. Sharp N.O.D. - Virginia Power l

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