ML17347B257
| ML17347B257 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 08/03/1989 |
| From: | Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17347B256 | List: |
| References | |
| 50-250-89-27, 50-251-89-27, NUDOCS 8908180034 | |
| Download: ML17347B257 (3) | |
Text
ENCLOSURE 1
NOTICE OF VIOLATION Florida Power and Light Company Turkey Point Units 3 and 4
Docket Nos. 50-250, 50-251 Licensee Nos.
DPR-31, DPR 41 During the NRC inspection conducted on May 27 - June 30, 1989, violations of NRC requirements were identified.
The violations involved:
One example of failure to meet the requirements of Technical Specification (TS) 6.8. 1, in that failure to follow procedure resulted in two separate safeguards actuations within a 24-hour period; and one example of failure to meet the requirements of 10 CFR 50, Appendix B, Criterion III, in that non-conservative acceptance criteria was used for Power Operated Relief Valve (PORV) opening times.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Action",
Appendix C (1989),
the violations are listed below:
a
~
TS 6.8.1 requires that written procedures and administrative policies shall be established, implemented and maintained that meet or exceed the requirements and recommendations of Appendix A of USNRC Regulatory Guide 1.33 and Sections
- 5. 1 and 5.3 of ANSI N18.7-1972.
Administrative Procedure O-ADM-209, Equipment Tagging and Labeling, provides the responsibilities, precautions, limitations and instructional guidance for establishing and maintaining an accurate, complete and effective plant tagging program.
Contrary to the
- above, engraved label plates were replaced on the Unit 3 Safety Injection Block Switch without following the require-ments of Administrative Procedure O-ADM-209, resulting in two separate safeguard actuations within a 24-hour period.
This is a Severity Level IV violation (Supplement I).
b.
10 CFR 50, Appendix B, Criterion III, as implemented by the approved Florida Power and Light Company Topical Quality Assurance Report (FPLTQAR) 1-76A, Revision II, Topical Quality Requirement (TQR) 3.0, Revision 7,
requires that measures be established to assure that applicable regulatory requirements and the design basis are correctly translated into specifications, drawings',
procedures, and instructions.
Contrary to the above, the required 2.0 second opening time specified for the Pressurizer Power Operated Relief Valve (PORV) in the Overpressure Mitigating System (OMS) Safety Evaluation Report dated March 14,
- 1980, was not incorporated into the licensee's Inservice Testing Program.
- Instead, a non-conservative acceptance criteria of 15.0 seconds was used.
This resulted in the Unit 3 and 4
PORVs being gqp818'0034 8><pp250 qo803 pgp PDOCV, 0 p~g 6
Florida Power and Light Company Turkey Point Uni.ts 3 and 4
Docket Nos. 50-250, 50-251 Licensee Nos.
DPR-31, DPR 41 unable to maintain Reactor Coolant System (RCS) pressure below the
'0 CFR 50, Appendix G limits, had the most limiting design basis transient occurred.
This condition existed on several occasions from May 1984 to June
- 1988, as exhibited by a review of PORV stroke timing records.
0 This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Florida Power and Light Company is hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN:
Document Control
- Desk, Washington, DC
- 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, Turkey Point, within 30 days of the date of the letter transmitting this Notice.
This reply should be clearly marked as a "Reply to a Notice of Violation" and should include (for each violation):
(1) admission or denial of the violation, (2) the reason for the violation if admitted, (3) the corrective steps which have been taken and the results
- achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved.
Where good cause is
- shown, consideration will be given to extending the response time.
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 not be modified, suspended, or revoked or why such other action as may be proper should not be taken.
FOR THE NUCLEAR REGULATORY COMMISSION ups A. Reyes, Director Division of Reactor Projects Dated at Atlanta, Georgia this 3rd day of August 1989