ML17053C577
| ML17053C577 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 04/20/1981 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | NIAGARA MOHAWK POWER CORP. |
| Shared Package | |
| ML17053C578 | List: |
| References | |
| NUDOCS 8105010576 | |
| Download: ML17053C577 (14) | |
Text
7590-01 UNITED STATES OF AMERICA NUCI EAR REGULATORY COMMISSION In the Matter of
)
NIAGARA MOHAWK POWER CORPORATION (Nine Mile Point Nuclear Station, Unit 1)
)
Docket No. 50-220 ORDER FOR MODIFICATION OF LICENSE The Niagara Mohawk Power Corporation (the licensee) holds Facility Operating License No. DPR-63, which authorizes the licensee to operate the Nine Mile Point Nuclear Station, Unit 1 (the facility) at power levels not in excess of 1850 megawatts thermal.
The facility, which is located at the licen-see's site in Oswego County, New York is. a boiling water reactor.(BWR) used for the commercial generation of electricity.
The Reactor Safety Study (RSS),
WASH-1400, identified in a PWR an inter-system loss of coolant accident (LOCA) which is a significant contributor to risk of core melt accidents (Event Y).
The design examined in the RSS contained in-series check valves isolating the high pressure Primary Coolant System (PCS) from the Low Pressure Injection System (LPIS) piping.
The scenario which leads to the Event V accident is initiated by the failure of these check valves to function as a pressure isolation barrier.
This causes an overpressurization and rupture of the LPIS low pressure piping which results in a LOCA that bypasses containment.
7590-01
~
2 w
In order to better define the Event V concern, all light water reactor licensees were requested by letter dated February 23, 1980, to provide the following in accordance with 10 CFR 50.54(f):
1.
Describe the valve configurations and indicate if an Event V isolation valve configuration exists within the Class I boundary of the high pressure piping conn cting PCS piping to low pressure system piping; e.g.,
(1) two check valves
'n
- series, or (2) two check valves'in series with a motor operated valve (MOY);
- 2. If either of the above Event Y configurations exist, indicate whether. continuous surveillance or periodic tests are being performed on such valves to ensure integrity.
Also indicate whether valves have been known, or found, to lack integrity; and
- 3. If either of the above Event V configurations exist, indicate whether plant procedures should be'evised
- or if plant modifications should be made to increase'eliability.
In addition to the above,'icensees were asked to perform individual check valve leak testing prior to plant startup after the next. scheduled outage.
By letter dated Narch 19, 1980,.the licensee responded to our February letter.
- Based upon the NRC review of this response as well as the review of previously docketed=information for your facility, I have concluded in consonance with the attached Safety Evaluation (Attachment 1) that one or more valve configura-tion(s) of concern exist at the facility.
The a.tached Technical Evaluation Report (TER)'Attachment
- 2) provides, in Section 4.0, a tabulation of the subject valves.
7590-01 The staff's concern has been exacerbated due not only to the large number of plants which have an Event V configuration(s) but also because of recent unsatisfactory operating experience.
Specifically, two plants have leak tested check valves with unsatisfactory results.
At Davis-Besse, rr a pressure isolation check valve in the LPIS failed and the ensuing investigation found that valve internals had become disassembled.
At the Sequoyah Nuclear Plant, two Residual Heat Removal (RHR) injection check
\\
valves and one RHR recirculation check valve failed because valves jammed open against valve over-travel limiters.
It is, therefore, apparent that when pressure isolation is provided by two in-series check valves and when failure of one valve in the pair can go undetected for a substantial length of time, verification of valve integrity is required.
Since these valves are important to safety, they should be tested periodically to ensure low probability of gross failure.
As a result, I have determined that periodic examination of check valves must be undertaken by the licensee as provided in Section III below to verify that each valve is seated properly and functioning as a pressure isolation device.
Such testing will reduce the overall risk of an inter-system LOCA.
The testing mandated by this Order may be accomplished by direct volumetric leakage measurement or by other equivalent means capable of demonstrating that leakage limits are not exceeded in accord-ance with Section 2.2 of the attached TEP.
7590-01 In view of the operating experiences described above and the potential consequences of check valve failure, I have determined that prompt action is necessary to increase the level of assurance that multiple pressure isolation barriers are in place and will remain intact.
Therefore, the public health, safety and interest require that this modification of Facility Operating License No. DPR-63 be immediately effective.
Accordingly, pursuant to Section 16li of the Atomic Energy Act of 1954, as
- amended, and the Commission's regulations in 10 CFR Parts 2 and 50, IT IS HEREBY ORDERED THAT EFFECTIVE IMMEDIATELY,Facility Operating License No. DPR-63 is modified by the addition of the following requirements:
l.
Implement Technical Specifications (Attachment 3 ) which require periodic surveillance over the life of the plant and which specify limiting conditions for operation for PCS pressure isolation valves.
- 2. If check valves have not been (a) individually tested within 12 months preceding the date of the Order, and (b) found to comply with the leakage rate criteria set forth in the Technical Specifications described in Attachment3, the MOV in each line shall be closed within 30 days and quarterly Inservice Inspection
( ISI)
MOV cycling ceased until the check valve tests have been satisfactorily accomplished.
(Prior to closing the MOV, procedures shall be implemented and operators trained to assure
1 I
7590-01 that the MOV remains closed.
Once closed, the MOV shall be tagged closed to further preclude inadvertent valve opening.)
3.
The MOV shall not be closed as indicated in paragraph 2
above unless a supporting safety evaluation has been prepared to determine whether closing the MOV results in an unreviewed safety question during plant operation.
If the safety evaluation results in a determination that no unreviewed safety question exists as defined in 10 CFR 50.59(a)(2),
the MOV shall be closed as indicated in paragraph 2 above. If the safety evaluation results in a finding that closing the MOV does present an unreviewed safety question pursuant to 10 CFR 50.59(a)(2),
the facility shall be shut down within 30 days of the date of this Order and remain shut down until check valves are satisfactorily tested in accordance with the Technical Specifications set forth in Attachment 3.
4.
The records of the check valve tests required by this,Order shall be made available for inspection by the NRC's Office of Inspection and Enforcement.
7590-01 IV The licensee or any other person who has an interest affected by this Order may request a hearing on this Order within 25 days of its publication in the Federal Register..
A request for hearing shall be submitted to the Secretary, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555.
A copy of the request shall also be sent to the Executive Legal Director at the same address, and to Eugene B. Thomas, Jr., Esquire,
- LeBoeuf, Lamb, Lieby and MacRae, 1333 New Hampshire Avenue, NW, Suite 1100, Washington, DC
- 20036, attorney for the licensee.
If a hearing is requested by a person other than the licensee, that person shall describe, in accordance with 10 CFR 2.714(a)(2),
the manner in which his or her interest is affected by this Order.
ANY REQUEST FOR A HEARING SHALL NOT STAY THE IMMEDIATE EFFECTIVENESS OF THIS ORDER.
If a hearing is requested by the licensee or other person who has an interest affected by this Order, the Commission will issue an order designating the time and place of any such hearing.
If a hearing is held, the issues to be considered at such a hearing shall be:
(a) Whether the licensee should be required to individually leak test check valves in accordance with the Technical Specifications set forth in Attachment 3 to this Order.
(b) Whether the actions required by Paragraphs 2 and 3 of section III of this Order must be taken if check valves have not been tested within 12 months preceeding the date of this Order.
7590-01 7
Operation of the facility on terms consistent=with this Order is not stayed by the pendency of any proceedings on this Order.
In the evept that a need for further action becomes
- apparent, either in the course of proceedings on this Order or any other time, the Director will take appropriate action.
FOR TME NUCLEAR REGULATORY COMMISSION Effective Date:
April 20, 1981
- Bethesda, Maryland, Attachments:
1.
Safety Evaluation Report 2.
Technical Evaluation Report 3.
Technical Specifications Darre1 l G.
'enhut, Director Division of Licensing