ML20207T090

Forwards Answers to Questions 2,6 & 12 of Recipient Re Recent Accident at Facility.Most of Requested Info Provided on 870129

ML20207T090
Person / Time
Site:	Surry
Issue date:	02/25/1987
From:	Zech L NRC COMMISSION (OCM)
To:	Markey E HOUSE OF REP.
References
NUDOCS 8703230179
Download: ML20207T090 (10)

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CHAIRMAN

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The Honorable Edward J. Markey United States House of Rrocesentatives Washington, O. C. 10515

Dear Congressman Markov:

On lanuary 29, 1987 I providad most of the information vou recuested concerning the recent accident a* tha-Surry Nuclear Power Station. I am anclosing answers tn cuestions 2, 6 and 12 of vour December 18, 1996 latter.

Sincerely, y N- W I Lando 'd . Zecp/,.ir.J e

Enclosure:

As Stated i

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RESPONSE TO CONGRESSMAN MARKEY

- CATASTROPHIC PIPE FAILURE AT SURRY 2 QUESTION 2.

Please provide an Operational History of the Surry Facility. Include in this History a Chronology of all notices of unusual events and all enforcement actions taken against the facility.

ANSWER.

A brief operational history of the Surry power station is presented in Attachment 1. A list of all unusual events reported by the licensee to the NRC Operations Center in accordance with 10 CFR 50.72 is presented in Attachment 2. The information on enforcement actions was provided in the initial response.

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Attachment 1 RRIEF.QPERATIONAL HISTORY OF THE SURRY POWED STATION UNIT 1:

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Surry 1 was taken critical for 'the first time on July 1, 1972, and was declared to be in commercial operation on December 2?, 1977 As of Julv 31, 1986, the latest date for which tabulated, data are available, the plant had generated a lifetime total of 52,496,477 Vegawatt-hours of alectrical energy.

In 1972 there were no significant outages on Surry 1.

In 1973, the unit experienced orchlems with fuel densification, and onwer was limited to 75 percent through March. _in v arch the restriction was revised to 92 percent, and in Aucust normal reactor plant coerating pressure was reduced from 2250 psig to ?000 osio, and the power restriction renoved. A reactor coolant pump motor ~was replaced in May. In iluly and October, rapairs were made on main steam trip valves. A reactor coolant oump shaft sheared and_a main coolant cutout valve sten broke. Depair efforts on these items lasted until March 1974 The #irst refueling of Surry 1 took clace from october 1074 through February 1975.

The second refuelina occurred fron October to December 1975.

Surry 1 experienced stear generator tube leaks ir March, April, July,-

August, ard Seotenber 1976. The third refuelina took olace from October 1976 to January 1977.

Steam aanerator insoec+ ion and tube plugging was cer#nened in April and

'lovember 1977.

The fcurth refueling of Surry 1. was undartakan Aorii throuch .luiv 1078, and in December of that vear the unit experiencad another steam canara*nr tube leak.

?urirg March throuch Septamber 1974, Surrv 1 underwert oioiro seismic nodifications as per IE Bulletin 79-14 From necachar 1970 to January 1980 a reactor coolant pump motor was replaced.

Additional piping seismic modifications wore mada # rom ebruary to Vav 1980. From September 1980 throuch Julv 1981 all threa s* ear qenerators wera reolaced and the unit was refueled #ne the 'i'th time.

In September 1981 Surry 1 experienced an auxiliarv 'eecwatar laak, ard in November a reactor coolant nump motor was chanced.

Thera were no significant ou+aqes for +he unit in 1999 Defueling number six took clace February tn . lure 1983.

Snubber repairs were undertaken in March and April 1984 In .1une Surry I exoerienced a stuck control rod and oower was limited to 80 narcent. 'he unit's seventh refuelino took olace durinq 9entarber througn Dacamber 19F4

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Surry 1 h'ad no significant outages in 1985.

Refuejing number eight was conducted from May to July 1986.

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UNIT 2:

Surry 2 was taken critical for the first time on March 7,1973, and was declared to be in commercial operation on May 1, 1973. As of July 31, 1986, the latest date for which tabulated data are available, the plant had generated a lifetime total of 53,787,325 Megawatt-hours of electrical energy.

In 1973, the unit experienced problems with fuel densification, and power was limited to 92 percent. In August normal reactor plant operating pressure was reduced from 2250 psig to 2000 psig, and the power restriction removed.

Surry 2 was shut down from April through June 1974 for reactor coolant pump shaft replacement. From September 1974 to January 1975 repairs were made on broken blades in the main turbine.

The first refueling of Surry 2 took place April through June 1975.

Steam generator tube leaks were experienced in January,. February, March, September, and December 1976. Refueling number two occurred from April to June 1976.

Additional steam generator tube leaks were experienced and tubes were plugged in February, July, and November 1977. The unit's third refueling took place in September and October 1977.

Steam generator inspection was performed in March 1978, and emergency core cooling pump modifications were made in July.

From February 1979 until August 1980, Surry 2 was shut down for its fourth refueling, replacement of all three steam generators, and piping seismic modifications as per IE Bulletin 79-14.

Plant modifications based on the lessons learned from the Three Mile Island Accident were installed and snubber inspections made in April 1981. The unit was refueled for the fifth time and feedwater heater repairs were made in November and December.

There were no significant outages for Surry 2 in 1982.

Refueling number six took place June to Saptember 1983. In December of this year repairs were made on an auxiliary feedwater system check valve and on reactor coolant pump seals.

Snubber repairs were undertaken in March and April 1984 Surry 2 was refueled for the seventh time March through June 1985.

Steam generator tube leaks were plugged in June and July 1986.

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9 Attachment 2 LIST 0F UNUSUAL EVENTS REPORTED BY SURRY POWER STATION

1. Event 07140, 12/9/86, Failure of main feedwater pipe and 3 critical injurlei.- .

2. Event 05587, 7/22/86, TGbe leak in recirculation spray heat exchanger.

3. Event 05543, 7/19/86, Security event.

4. Event 05086, 6/17/86, Service water leak from a recirculation spray heat exchanger return line.

5. Event 04820, 5/28/86, Release of radioactivity.

6. Event 01549, 7/23/85, Release of radioactivity.

7. Event, 12/18/84, Fire in diesel generator room.

8. Event, 5/8/84, Loss of power to meteorological tower and NRC telephone.

9. Event, 2/25/84, Release of radioactivity.

10. Event, 9/26/83, Release of radioactivity.

11. Event, 4/1/83, Contaminattd injury.

12. Event, 12/22/82, Release of radioactivity.

13. Event, 8/26/82, Release of radioactivity.

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Provide the Subcommittee.with a Pecent IJpda*.a en the einding's of-the Augmented Insoaction Team's Investinatinn of tha Accident. . In addition, orovide tha Subcommd+taa.with a draft

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copy of'this report as soon as it has been c oir o ' e t e d .

ANSFER The NRC's Augnented Inspection Tean's Daonr* is' attached, fSea Attachment 3)

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QUESTION 12. ,

Provide the sdhcommittee_with al1 correspondence between the NRC and Virginia Power regarding the pipina system and steam-related accidents at Surry sinca 1972. In addition, provide the subconnittee with all correspondence between NRC and Virginia Power after the report n' the accident.

ANSWER.

Correspondence regarding the piping system and steam related accidents is in provided in Attachment 4 All correspondence between NRC and Virginia Pcwer after the report o' the accident and orior to ilaruary 15, 1987, is in Attachment 5.

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Attachment 4 CORRESPONDENCE RE THE PIPING SYSTEM AND STEAM RELATED ACCIDENTS

. . . 1972 TO PRESENT

1. Letter, Virginia Electric and Power Co (VEPCO) to NRC's Office of Nuclear Reactor. Regulation (NRR),-12/23/86, Action in response to Surry 2 feedwater line rupture. __

2. Letter, VEPCO to NRC's Directorate of Licensing (DL), 11/16/72, Operating incident of 7/27/72.

3. Letter, DL to VEPCO, 10/11/72, Operating incident of 7/27/72.

4. Letter, VEPC0 to DRP, 8/16/72, Operating incident of 7/27/72 resulting in two fatalities, d

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d Attachment 5 ALL CORRESPONDENCE BETWEEN NRC AND VIRGINIA POWER

.BE, TWEEN DECEMBER 9, 1985 AND JANUARY 15, 1987

1. Letter, Virginia Electric and Power Company (VEPCO) to NRC's Office of Nuclear,-Regulation (NRR), 12/10/86, Additional information regarding 40 year operating licenses.

2. Letter, NRC Region II to VEPCO, 12/11/86, Systematic assessment of licensee performance.

3. Letter, VEPCO to NRR, 12/11/86, Security program.

4. Letter, VEPC0 to NRR, 12/12/86, Pressurized thermal shock.

5. Letter, VEPC0 to NRC, 12/13/86, Submittal of Licensee Event Report (LER) 86-033-00, Containment air partial pressure.

6. Letter, VEPC0 to Region, 12/15/86, Potential failure of ECCS pumps.

7. Letter, VEPC0 to NRC, 12/15/86, Submittal of LER 86-016-00, Closure of containment radiation monitoring valves.

8. Letter, VEPCO to NRC, 12/15/86, Submittal of LER 86-034-00, Clogging of service water strainer for control room chiller.

9. Letter, VEPC0 to NRC, 12/15/86, Submittal of LER 86-017-00, Auto-start of diesel generator.

10. Letter, VEPC0 to NRC, 12/16/86, Submittal of LER 86-023-02, Containment sump trip valve.

11. Letter, NRC Region II to VEPCO, 12/22/86, Environmental monitoring program.

12. Letter, VEPC0 to NRR, 12/23/86, Impact of Surry 2 accident on request for amendment of 40 year operating license.

13. Letter, VEPC0 to NRC Region II, 12/23/86, Amendment to emergency plan.

14. Letter, NRC Region II to VEPCO, 12/23/86, Incident investigation and performance indicators.

15. Letter, VEPC0 to NRC,12/29/86, Submittal of LER 86-019-00, Rod position indicators out of calibration.

16. Letter, NRR to VEPC0, 12/30/86, Environmental Assessment for 40 year operating license.

17. Letter, NRC Region II to VEPCO, 12/30/86, Inspection Report.

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18. Letter, NRA'to VEPCO, 12/31/86, Extension of Surry operating licenses.

19. Letter c.YEPC0 to NRR, 12/31/86, Updated final safety analysis report.

20. Letter, Nuclear Regulatory Research to VEPCO, 1/12/87, Probabilistic risk assessment.

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