ML20083C864
| ML20083C864 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/13/1983 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | CAROLINA POWER & LIGHT CO. |
| Shared Package | |
| ML20083C867 | List: |
| References | |
| IEB-82-03, IEB-82-3, IEB-83-02, IEB-83-2, NUDOCS 8312270075 | |
| Download: ML20083C864 (65) | |
Text
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
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Docket No. 50-324
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CAROLINA POWER & LIGHT COMPANY (Brunswick Steam Electric
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Plant, Unit 2)
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ORDER CONFIRMING CAROLINA POWER & LIGHT COMPANY COMMITMENT RE IGSCC INSPECTION I.
The Carolina Power & Light Company, (the licensee, CP&L) is the holder of Facility Operating License No. DPR-62, which authorizes the licensee to operate the Brunswick Steam Electric Plant, Unit 2 (the facility), at power levels not in excess of 2436 megawatts thermal. The facility is a boiling water reactor located at the licensee's site in Brunswick County, North Carolina.
II.
As a result of inspections conducted at 18 operating boiling water reactors (BWRs) in coiformance with recent IE Bulletins (IE Bulletin No. 82-03, Revision 1, " Stress Corrosion Cracking in Thick-Wall, large-Diameter, Stainless Steel, Recirculation System Piping at BWR Plants," and IE Bulletin No. 83-02, " Stress Corrosion Cracking in large-Diameter Stainless Steel Recirculation System Piping at BWR Plants"), a potential safety concern regarding intergranular stress corrosion cracking (IGSCC) in primary systen piping was identified. These bulletins reouested selected licensees to
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perform a number of actions regarding inspecticn and testing of pipe welds.
8312270075po 4
. Results of these and other inspections pursuant to IE Bulletins 82-03 and 83-02 have revealed. extensive cracking in large-diameter recirculation and residual heat removal system piping.
In almost every caer. where inspec-tions were performed, IGSCC was discovered and, in many cases, repairs, analysis, and additional surveillance conditions were required.
In view of the foregoing and the fact that the facility is similar in design to plants where IGSCC has occurred, there was a significant potential for IGSCC to exist in this facility. Therefore inspection was required to determine the extent of IGSCC and to ascertain, if necessary, the degree of remedial action.
On August 26, 1983 an Order was issued to the licensee which required th~at the facility be shutdown by November 1, 1983 and an IGSCC inspection be per-formed (this Order was modified on October 28, 1983 to allow the shutdown to be as late as November 9, 1983).
On November 2,1983 the facility was shutdown pursuant to Section III.B of the Order and an IGSCC inspection was performed pursuant to Section III.C of the August 26, 1983 Order.
In a November 28, 1983 report, as supplemented by two letters each dated November 30, 1983, the licensee discussed its IGSCC inspection pursuant to Section III.C.5 of the Order. This report concluded, based on certain compensatory action and the inspection results, that operation of the facility was justified through April 30, 1983.
The staff review of the licensee's report dated November 28, 1983 as supplemented by two letters dated November 30, 1983, has been completed and
. is docunented in the Safety Evaluation dated December 13, 1983. The NRC letter dated December 13, 1983 notified the licensee that the facility could be returned to power. Although the calculations discussed in the above report indicate that the cracks in the 8 overlay repaired welds or the 11 unrepaired welds will not progress to the point of leakage during the remainder of this fuel cycle, and margins are expected to be maintained over crack growth which could compromise safety, uncertainties in crack sizing and growth rate still remain.
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Because of these uncertainties, we have detiennined that improvements in the monitoring in the containment for unidentified leakage are required; there-fore, the changes to the limiting conditions for operation and surveillance requirements imposed by the August 26, 1983 Order should be continued.
These enhanced surveillance measures will provide adequate assurance that possible cracks in pipes will be detected before growing to a size that will compromise the safety of the plant.
The staff also has some concern regarding the long-term growth of IGSCC cracks and its effect on the long-term operation of the plant. Therefore, we have determined that plans for inspections, corrective action and/or modification including replacement of the recirculation and other reactor coolant pressure boundary piping systems during the next refueling outage must be submitted at least 30 days before the start of the next refueling outage.
Ir. addition, the staff has determined that a justification for continued operation must be submitted to NRC for review and approval prior to startup after the next refueling outage.
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- By letter dated November 28, 1983, as supple,mented by two letters each dated November 30, 1983, the licensee comitted to the above described conditions on leakage monitoring and early submittal of inspection and/or modification plans.
I have determined that the public health and safety requires that these comitments should be confirmed by an immediately effective Order.
4 III.
Accordingly, pursuant to sections 103, 1611, 1610, 182 and 186 of the Atomic Energy Act of 1954, as amended, and thc Comission's regulations in 10 CFR Parts 2 and 50, IT IS HEREBY ORDERED EFFECTIVE IMMEDIATELY THAT:
A.
Notwithstanding the current Technical Specifications for the facility the following compensatory measures shall be implemented:
1.
The reactor coolant system leakage shall be limited to a 2 gpm increase in unidentified leakage within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period (leakage shall be monitored and recorded once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />).
Should this leakage limit be exceeded, the unit shall immediately start an orderly shutdown.. The unit shall be placed in at least hot shut-down within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2.
At least one primary containment sump collectien and flow monitoring system shall be operable. With the primary containment sump collec-tion and flow monitoring system inoperable, restore the inoperable system to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or immediately initiate an orderly shutdown and be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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_5-B.
The licensee shall place the facility in cold shutdown by April J0,1984.
C.
Plans for inspections, corrective actions, and/or modification, includ-ing replacement of the recirculation and/or coolant pressure boundary piping systems, during the next outage which is scheduled to begin in March 1984 but which may begin as late as April 30, 1984 shall be submitted at least 30 days before the start of that outage.
D.
At least one month prior to startup of the facility after its next refueling outage,.a justification for continued operation shall be submitted for NRC review and approval.
E.
The Director, Division of Licensing, may, in writing, relax or terminate any of the above provisions upon written request from the licensee, if the request is timely and provides good cause for the requested action.
IV.
The licensee may request a hearing on this Order within 20 days of the date of publication of this Order in the Federal Register. Any request for a hearing shall be addressed to the Director, Office of Nuclear Reactor Regulation, U. S. Nuclear Regulatory Commission, Washington, D. C.
20555.
A copy shall also be sent to the Executive Legal Director at the same address. A RE0 VEST FOR HEARING SHALL NOT STAY THE IMMEDIATE EFFECTIVENESS OF THIS ORDER.
If a hearing is to be held, the Commission will issue an Order designating the time and place of any such hearing.
If a hearing is held concerning this Order, the issue to be considered at the hearing shall be whether, on the basis of the matters set forth in Section II of-the Order, the licensee should comply with the requirements set forth in Section III of this Order. This Order is effective upon issuance.
OR THE NUCLEAR REGULATORY COMMISSION c i. ' l Il T '
1))a.}Eisenhut, Director
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arr Division of Licensing Dated at Bethesda, Maryland this 13 day of December,1983.
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