ML16342D613
| ML16342D613 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 04/29/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML16342D612 | List: |
| References | |
| 50-275-97-02, 50-275-97-2, 50-323-97-02, 50-323-97-2, NUDOCS 9705060323 | |
| Download: ML16342D613 (4) | |
Text
ENCLOSURE 1 NOTICE OF VIOLATION Pacific Gas and Electric Company Diablo Canyon Nuclear Power Plant Docket Nos.:
License Nos.:
50-275 50-323 DPR-80 DPR-82 During an NRC inspection conducted on February 2 through March 15, 1997, one violation of NRC requirements was identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violation is listed below:
A.
10 CFR Part 50, Appendix B, Criterion III, requires that regulatory requirements and the design basis, as defined in Section 50.2, are correctly translated into specifications, drawings, procedures, and instructions.
Contrary to the above, as of March 7, 1997, and April 2, 1996, for the refueling water storage tank level instrumentation and spont fuel pool temperature limits respectively, the licensee failed to assure that the design bases were correctly translated into procedures and instructions.
Specifically, 0
(1)
FSARU Section 6.3.1.4.4.1 states that two of three channels of refueling water storage tank (RWST) level instrumentation will automatically trip the residual heat removal (RHR) pumps on low RWST level.
In addition, Section 6.3.2.11 states that the emergency core cooling system is designed to withstand any single credible failure during the injection phase of a loss-of-coolant accident (LOCA).
The licensee's procedures and instructions did not provide adequate control to assure the availability of the automatic trip of the RHR pumps or the ability to withstand a single failure when one level instrument was taken out of service and put into the tripped condition.
As a result, from August 14-26, 1992, while Unit 2 was in Mode 1, RWST Level Transmitter 920 was out of service and provided an invalid trip signal to the RHR pum" trip logic.
In the event of a postulated design bases LOCA and the failure of one of the remaining operable level instruments, the RHR pumps would have tripped when required to operate.
(2)
The spent fuel pool criticality analysis submitted to the NRC in License Amendment Request (LAR) 95-01 used 68'F as the design basis lower temperature limit. However, the minimum design basis spent fuel pool temperature was not translated into procedures for maintaining spent fuel pool temperature.
As a result, the licensee's review determined that spent fuel pool temperatures have in the past decreased below 68'F.
3)
The spent fuel pool criticality analysis submitted to the NRC in LAR 95-01 referenced a temperature of 150'F as the high temperature value for normal conditions.
The licensee's analysis for full core offloads, which had become 97050b0323 970429 PDR ADOCK 05000275 8
PDR the licensee's normal practice during refueling, indicated that under the most limiting conditions the temperature of the spent fuel pool could reach 175 F.
The design basis limit of a maximum spent fuel pool temperature of 150 F
for normal conditions, specified in the criticality analysis submitted with LAR 95-01, was not translated into the licensee's procedures.
These are examples of a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Pacific Gas and Electric Company is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region IV, 611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011, and a copy to the NRC Resident Inspector at the facility that is the suoject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each violation:
(1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the required response.
If an adequate reply is not received within the time specified in this Notice, an order or a Demand for Information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken.
Where good cause is shown, consideration will be given to extending the response time.
Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction.
However, if you find it necessary to include such information, you should clearly indicate the specific infor... tion that you desire not to be placed in the PDR, and provide the legal basis to support your request for withholding the information from the public..
Dated at Walnut Creek, California, this 29th day of'April 1997
ENCLOSURE 1 NOTICE OF VIOLATION Pacific Ga and Electric Company Diablo Cany n Nuclear Power Plant Docket Nos.:
License Nos.:
50-275 50-323 DPR-80 DPR-82 During an NRC insp ction conducted on February 2 through March 15, 1997, one violation of NRC requirements as identified.
In accordance with the "General Statement of Policy and Procedure for NR nforcement Actions," NUREG-1600, the violation is listed below:
A.
10 CFR Part 50, Ap endix B, Criterion III, requires that regulatory requirements and the design basis, as fined in Section 50.2, are correctly translated into specifications, drawing 'rocedures, and instructions.
Contrary to the above, as f March 7, 1997, and April 2, 1996, for the refueling
'ater storage tank level inst mentation and spent fuel pool temperature limits respectively, the licensee faile to assure that the design bases were correctly translated into procedures and i structions.
Specifically, (1)
FSARU Section 6.3.1.4.4.1 tates that two of three channels of refueling water storage tank (RWST) le I instrumentation will automatically trip the
. residual heat removal (RHR) pu s on low RWST level.
In addition, Section 6.3.2.11 states that the ergency core cooling system is designed to withstand any single credible fai re during the injection phase of a loss-of-coolant accident (LOCA).
The licensee's procedures and instructio did not provide adequate control to assure the availability of the automatic ip of the RHR pumps or the ability to withstand a single failure when on level instrument was taken out of service and put into the tripped condition.
s a result, from August
". '-26, 1992, while Unit 2 was in Mode, RWST Level Transmitter 920 was out of service and provided an invalid tn signal to the RHR pump trip logic.
In the event of a postulated design base LOCA and the failure of one of the remaining operable level instruments, the R pumps would have tripped when required to operate.
(2) 3)
The spent fuel,,pool criticality analysis submitted to the NR in License Amendment Request (LAR) 95-01 used 68'F as the design sis lower temperature limit. However, the minimum design basis spent el pool temperature was not translated into procedures for maintaining pent fuel pool temperature.
As a result, the licensee's review determined t t spent fuel pool temperatures have in the past decreased below 68OF.
The spent fuel pool criticality analysis submitted to the NRC in LAR 95-1 referenced a temperature of 150'F as the high temperatur'e value for nor al conditions.
The licensee's analysis for full core offloads, which had becorn
li iting conditions the temperature of the spent fuel pool could reach 175 F.
The sign basis limit of a maximum spent fuel pool temperature of 150'F for nor al conditions, specified in the criticality analysis submitted with LAR 95-1, was not translated into the licensee's procedures.
These are example of a Severity Level IV violation (Supplement I).
Pursuant to the provisions o 10 CFR 2.201, Pacific Gas and Electric Company is hereby required to submit a written st tement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document ontrol Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region I, 611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011, and a copy to the NRC Res ent Inspector at the facility that is the subject of this Notice, within 30 days of the date o the letter transmitting this Notice of Violation (Notice). This reply should be clearly arked as a "Reply to a Notice of Violation" and should include for each violation:
(1) th reason for the violation, or~.if contested, the basis for disputing the violation, (2) the c rective steps that have been taken and the results achieved, (3) the corrective steps th t will be taken to avoid further violations, and (4) the date when full compliance will be.ach ved.
Your response may reference or include previous docketed correspondence, if e correspondence adequately addresses the required response.
If an adequate reply is not r eived within the time specified in this Notice, an order or a Demand for Information ma be issued as to why the license should not be modified, suspended, or revoked, or why su other action as may be proper should not be taken.
Where good cause is shown, consider ion will be given to extending the response time.
Because your resoonse will be placed in the NRC Public D cument Room (PDR), to the extent possible, it should not include any personal privacy, roprietary, or safeguards information so that it can be placed in the PDR without"redac on.
However, if you find it necessary to include such information, you should clea'rly indic te the specific information that you desire not to be placed in the PDR, and provide the Iega basis to support your request for withholding the information from the public."
Dated at Walnut Creek, California, this 15th day of April 1997