ML18153A842

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Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-280/95-06 & 50-281/95-06
ML18153A842
Person / Time
Site: Surry  Dominion icon.png
Issue date: 06/09/1995
From: Merschoff E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Ohanlon J
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
References
NUDOCS 9506190438
Download: ML18153A842 (7)


See also: IR 05000280/1995006

Text

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June 9, 1995

Virginia Electric and Power Company

ATTN:

Mr. J. P. O'Hanlon

Senior Vice President - Nuclear

Innsbrook Technical Center

5000 Dominion Boulevard

Glen Allen, VA

23060

SUBJECT:

NRC INSPECTION REPORT NOS. 50-280/95-06 AND 50-281/95-06

Gentlemen:

Thank you for your response of May 15, 1995, to our Notice of Violation (NOV),

issued on April 14, 1995, concerning activities conducted at your Surry

facility.

We have examined your response and found that it meets the

requirements of 10 CFR 2.201.

In your response, you stated that you agree with the violation as stated in

the NOV.

You also state that you believe that the violation meets the

criteria for a non-cited violation as stated in 10 CFR 2, Appendix C,

VI I. 8(2).

After careful con*s i derat ion for the bases for your request to rec 1 ass i fy the

Severity Level IV violation to a non-cited violation, we have concluded, for

the reasons presented in the enclosure to this letter, that the violation was

correctly categorized as stated in the NOV.

We will examine the implementation of your corrective actions during future

inspections.

We appreciate your cooperation in this matter.

Docket Nos. 50-280, 50-281

License Nos. DPR-32, DPR-37

Enclosure:

Evaluations and Conclusions

cc w/encl: (see page 2)

Sincerely,

Orig signed by Ellis W. Merschoff

Ellis W. Merschoff, Director

Division of Reactor Projects

OFFICIAL COPY

9506190438 950609

PDR

ADOCK 05000280

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VEPCO

cc w/encl:

M. L. Bowling, Manager

Nuclear Licensing & Programs

Virginia Electric & Power Company

Innsbrook Technical Center

5000 Dominion Boulevard

Glen Allen, VA

23060

David A. Christian, Station Manager

Surry Power Station

P.O. Box 315

Surry, VA

23883

Ray D. Peace, Chairman

Surry County Board of Supervisors

P. 0. Box 130

Dendron, VA

23839

Dr. W. T. Lough

Virginia State Corporation Commission

Division of Energy Regulation

P. 0. Box 1197

Richmond, VA

23209

Michael W. Maupin

Hunton and Williams

Riverfront Plaza, East Tower

951 E. Byrd Street

Richmond, VA

23219

Robert B. Strobe, M.D., M.P.H.

State Health Commissioner

Office of the Commissioner

Virginia Department of Health

P. 0. Box 2448

Richmond, VA

23218

Attorney General

Supreme Court Building

101 North 8th Street

Richmond, VA

23219

2

VEPCO

Distribution w/encl:

B. Buckley, NRR

G. Hallstrom, RII

PUBLIC

NRC Resident Inspector

U.S. Nuclear Regulatory Commission

Surry Nuclear Power Station

5850 Hog Island Road

Surry, VA

23883

NRC Resident Inspector

U.S. Nuclear Regulatory Commission

Route 2, Box 78-A

Mineral, VA

23117

3

  • FOR PREVIOUS CONCURRENCE SEE ATTACHED

SIGNATURE

NAME

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DATE

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cc w/encl:

Continued

Rob t B. Strobe, M.D., M.P.H.

Stat Health Commissioner

Office of the Commissioner

Virgini Department of Health

P. 0. Bo

2448

Richmond, VA

23218

Attorney Ge ra l

Supreme Cour Building

101 North 8th treet

Richmond, VA

219

Distribution we

B. Buckley, NRR

G. A. Hallstrom,

PUBLIC

NRC Resident Inspect

U.S. Nuclear Regulate

Commission

Surry Nuclear Power St

5850 Hog Island Road

Surry, VA

23883

NRC Resident Inspector

U.S. Nuclear Regulatory

Route 2, Box 78-A

Mineral, VA

23117

SIGNATURE ,--.-/

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NAME

LGarner

GBelisle

DATE

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Robirt I, Strobe, M,D, 1 N.P.H.

Stat, Health C01111111s1on1r

Office of th, COll81sttoner

V1rg1nta Dtp1rt111ent of Htalth

P. 0, Box !4U

R1chiwond, VA 2)118

Atto'M!ay General

Suprt111 Court Bu11dinv

101 North 8th Street

R1ch11and, YA 23219

K~*~~t1~D""°a.'1.:

G. A, Hafistram, RIJ

PUBLIC

NRC Resident In1p1ctor

U.S. Nucl11r Regulatory Conn1111on

Surry Nuc11ar Pow1r St1t1on

9150 Hog J1l1nd Road

Surry' VA ZHU

NRC Re11d1nt Inspector

U.S. Nllcl,ar Regulatory Co111ission

Rout, Z, lox 71-A

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EVALUATIONS AND CONCLUSIONS

On April 14, 1995, a Notice of Violation {Notice) was issued for a violation

identified during a routine NRC inspection. Virginia Electric and Power

Company responded to the Notice on May 15, 1995.

The licensee stated that

they agreed that a violation occurred, but they believed that the violation

met the criteria for a non-cited violation as stated in 10 CFR 2, Appendix C,

VII.8(2).

The NRC's evaluations and conclusions regarding the licensee's

arguments are as follows:

Restatement of the Violation

Technical Specification 3.1.B.3, in part, requires that the pressurizer

heatup rate not exceed 100 degrees F per hour.

Contrary to the above, on February 4, 1995, the heatup rate of the

Unit 2 pressurizer exceeded 100 degrees Fin a one hour period.

From

10:30 a.m. to 11:30 a.m. the temperature in the pressurizer increased

from 254 to 400 degrees F, a change of 146 degrees F .

This is a Severity Level IV violation {Supplement I).

Summary of the Licensee's Response

Your response states that, "The violation was promptly identified by the

licensee as a result of increased monitoring of the pressurizer cooldown

rate by operations personnel during Reactor Coolant System (RCS)

cooldown activities. The additional monitoring was being performed in

response to recent industry events in which excessive RCS cooldowns

occurred.

The violation was not safety significant, and prompt

corrective actions have been implemented, including initiating an

engineering evaluation and instituting actions to prevent recurrence.

In fact, prompt restoration of temperature limits and performance of an

engineering evaluation to determine the effects of exceeding the limit

is the required action specified in Standard Technical Specifications

for this condition. Furthermore, excessive RCS heatups and cooldowns

are a recent generic issue in the industry and are currently being

evaluated for additional industry action by the Westinghouse owners

Group.

Therefore, we request reclassification of the cited Level IV

violation to a non-cited violation in accordance with the NRC

Enforcement Policy."

NRC Evaluation

The staff has carefully reviewed the licensee's request and has

concluded that the licensee did not provide any information that was not

already considered in determining the significance of the violation.

Enclosure

' -*

' .

2

10 CFR 2, Appendix C, VII.8(2), Licensee Identified Severity Level IV

and V violations, states that the NRC may refrain from issuing a Notice

of Violation for a Severity Level IV or V violation that is documented

in an inspection report .... and that the violation meets all of the

following criteria:

It was identified by the licensee ....

It was not a violation that could reasonably be expected to have

been prevented by the licensee's corrective action for a previous

violation or a previous licensee finding ....

It was or will be corrected within a reasonable time frame ....... .

It was not a willful violation ....

Although the violation met the previously stated criteria, discretion

was not granted and the violation was issued to emphasize the need to

more fully evaluate multiple evolutions performed infrequently or for

the first time.

For schedular reasons, multiple evolutions were

performed simultaneously which presented unexpected operational

challenges to the operators. Specifically, a degasification evolution

affecting pressurizer pressure and temperature controls was being

performed at the same time that plant components also affecting

pressurizer pressure and temperature were being realigned in

preparations for an electrical surveillance test. Although the licensee

was sensitized to recent industry events involving pressurizer

temperature transients, they had not fully evaluated the effects of

these evolutions (such as the potential for heating up) occurring

simultaneously.

Had these evolutions been thoroughly evaluated as part

of the scheduling and planning effort, the pressurizer temperature

transient greater than allowed by Technical Specifications could have

been avoided.

Enclosure