ML17342A853
| ML17342A853 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 08/07/1987 |
| From: | Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17342A852 | List: |
| References | |
| 50-250-87-33, 50-251-87-33, NUDOCS 8708170463 | |
| Download: ML17342A853 (6) | |
Text
ENCLOSURE 1
NOTICE OF VIOLATION Florida Power and Light Company Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 License Nos.
DPR-31 and DPR-41 During the Nuclear Regulatory Commission (NRC) inspection conducted on June 22 July 20,
- 1987, violations of NRC requirements were identified.
The violations involved the failure to promptly evaluate the significance of an auxiliary feedwater system steam
- leak, the failure to meet Technical Specification requirements for reducing reactor protection trip settings, and the failure to establish, an adequate fire protection procedures In accordance with "General Statement of Policy and Procedure for NRC Enforcement Action,"
10 CFR Part 2, Appendix C ( 1987),
the violations are listed below.
A.
10 CFR 50, Appendix 8, Criterion XVI, as implemented by Florida Power and Light Topical Quality Assurance Report FPLTQAR 1-76A, Revision 10, and TQR 16.0, Revision 5, entitled Corrective Action, requires in part, that measures be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected.
FPLTQAR 1-76A defines significant conditions adverse to quality as
- failures, malfunctions, deficiencies or deviations in material and equipment and other nonconformances which require engineering evaluation and/or evaluation for reportabi lity as required by 10 CFR 50.55(e),
reportable occurrences (LERs) or 10 CFR 21 deficiencies.
Administrative procedure O-ADH-913, entitled Corrective Action for Conditions Adverse to Quality, revi sion dated July 15, 1986, specifies in section 5.3 that supervisors shall be alert to significant conditions adverse to quality when recommending or approving changes based on observed or reported discrepancies.
Contrary to the
- above, between July 14 and July 17,
- 1987, the licensee failed to report to appropriate levels of management the identification of a significant condition adverse to quality, the cause of the condition, and the corrective action taken.
Consequently, the safety significance of pinhole leaks in a weld on the train 1
AFIIt steam line was not promptly evaluated.
~
B.
This is is a Severity Level IV violation (Supplement I) and is applicable to Unit 4 only.
Technical Specification 3.2.6.h requires that, if the quadrant to average power tilt exceeds a value of 2 percent and the hot channel factors are not determined within two hours, then reactor power shall be reduced from rated power 2 percent for each percent of quadrant tilt.
4 8708170463 870807 PDR ADOCK 05000250 G
Cl
Florida Power and Light Company Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 License Nos.
DPR-31 and DPR-41 Technical Specification 3.2.6.i requires that, if after a further period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the quadrant to average power tilt is not corrected to less than 2 percent and the hot channel factors are not determined, then:
- 1) the Nuclear Regulatory Commission shall be notified; and
- 2) the overpower differential temperature (OPDT) and overtemperature differential temperature (OTDT) trip settings shall be reduced by the equivalent of 2 percent power for every 1 percent quadrant to average power tilt.
Contrary to the
- above, between 12:Ol a.m.
on July ll and 7:05 p.m.
on July 12,
- 1987, a period of approximately 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br />, the quadrant to average power tilt exceeded 2 percent, the hot channel factors were not determined and the OPDT and OTDT trip settings were not reduced.
This is a Severity Level IV violation (Supplement I) and is applicable to Unit 4 only.
C.
Technical Specification 6.8. 1 requires that written procedures and administrative policies be established,,implemented and maintained that
'eet or exceed the requirements and recommendations of sections
- 5. 1 and 5.3 of ANSI N18.7-1972 and Appendix A of USNRC Regulatory Guide 1
~ 33.
Appendix A of USNRC Regulatory Guide 1.33 states that procedures should be established for the operation of plant fire protection equipment.
Operating Procedure 0-OP-016. 1, Fire Protection Water Systems, revision dated December 9,
- 1986, provides valve line-ups to control deluge systems.
Contrary to the above, procedure 0-OP-016. 1 was inadequate, in that it did not control the positions of pressure switch isolation valves for deluge systems for the Unit 3 and 4 component cooling water pump rooms and the A
and 8
Consequently, the pressure switch isolation valve for the Unit 3 component cooling water room was discovered to be isolated, preventing control room and local area deluge actuation alarms from functioning.
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 to this Office within 30 days of the date of the letter transmitting this Notice a written statement or explanation in reply including (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
. Flor'.da Power and Light Company Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 License Nos.
DPR-31 and DPR-41 be achieved.
Where good cause is
- shown, consideration will be given to extending the response time.
FOR THE NUCLEAR REGULATORY COMMISSION (Original signed by L. Reyes)
Dated at Atlanta, Georgia this 7th day of August 1987 Luis A. Reyes, Director
,Division of Reactor Projects
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