ML20034B915
| ML20034B915 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 04/17/1990 |
| From: | Richards S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20034B913 | List: |
| References | |
| 50-344-90-06, 50-344-90-6, NUDOCS 9005010158 | |
| Download: ML20034B915 (2) | |
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APPENDIX A NOTICE OF VIOLATION Portland General Electric Company Docket No. 50-344 Trojan Nuclear Plant License No. NPF-1 i
During an NRC inspection conducted from February 11 through March 24, 1990, two violations of NRC requirements were identified.
In accordance with the
" General Statement of Policy and Procedure for NRC Enforcement Actions," 10 l
CFRPart2,AppendixC(1989),theviolationsarelistedbelow:
l A.
Trojan Technical Specification 3.3.2 states, "The Engineered Safety l
Feature Actuation System (ESFAS) instrumentr. tion channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4 and with RESPONSE TIMES as shown in Table 3.3-5."
The " ALLOWABLE VALUES" column in Table 3.3-4 for high steam flow in two steam lines specifies " A function defined as follows: 44% of full steam
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L flow between 0% and 20% 1oad and then increasing linearly to 111.5% of full steam flow at full load."
Contrary to the above, from July 17, 1986 to March 20, 1990 Trojan was operated in modes 1, 2 and 3 with the steam flow trip setpoint function set at 40.87% of full steam flow between 0% and 20% load and then increasing linearly to 112.34% of full steam flow at full load.
This is a Severity Level IV violation (Supplement I).
B.
10 CFR Part 50, Appendix B, Criterion V, states in part:
" Activities affecting quality shall be prescribed by documented instructions, procedures or drawings, of a type appropriate to the circumstances and i
shall be accomplished in accordance with these instructions, procedures, I
or drawings."
The licensee's Nuclear Division Procedure (NDP) 600-0, " Corrective Action Program (CAP),"establishesthemethodstoidentify, evaluate, document, report and correct problems and nonconformances.
NDP 600-0. Section 5.2.B states that for a Corrective Action Request (CAR), Supervisors are responsible for the following:
2.
Assuring sufficient infonnation is indicated either on the CAR Form or on attachments so the condition can be accurately dispositioned, corrective actions taken and, where necessary, the item located."
Contrary to the above, on March 2, 1990 CAR C90-5007 was issued containing infonnation that Breaker B2245 was replaced, when in fact it had not been replaced.
This is a Severity Level IV violation (Supplement I).
9005010158 900417 PIsR ADOCK 05000344 Q
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j Pursuant to the provisions of 10 CFR 2.201, Portland General Electric Company is hereby required to submit a written statement of explanation to the U.S.
I Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555 with a copy to the Regional Administrator,. Region V, and a copy to the NRC Senior Resident Inspector, Trojan, within 30 days of the date of the letter transmitting this Notice.
This reply should be clearly marked as a l
" Reply to a Notice of Violation' and should include for each violation: (1) the reason for the violation if admitted (2) the corrective steps that have i
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 i
be achieved.
If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should l
not be modified, suspended, or revoked or why such other action as may be J
proper should not be taken.
Consideration may be given to extending the-response time for good cause shown.
FOR THE NUCLEAR REGULATORY COMMISSION
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i N S. A. Richards, Chief ReactorProjectsBranch Dated at Walnut Creek, California thisffdayofApril1990.
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