ML20198J129

Notice of Violation from Insp on 860407-11.Violations Noted: Failure to Collect Iodine & Particulate Samples Daily, Failure to Log Axial Flux Difference Hourly & Failure to Conduct Surveillances

ML20198J129
Person / Time
Site:	Diablo Canyon
Issue date:	05/12/1986
From:	Mendonca M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20198J127	List: IR 05000275/1986014 ML20198J122 ML20198J129
References
50-275-86-14, 50-323-86-15, NUDOCS 8605300689
Download: ML20198J129 (3)

Text

.

. s APPENDIX A NOTICE OF VIOLATION Pacific Gas and Electric Company Docket Nos. 50-275 and 50-323

_ Diablo Canyon Units 1 and 2 License Nos. DPR-80 and DPR-81 During an NRC inspection conducted on April 7-11, 1986, a violation of NRC requirements was identified. The violation involved Technical Specification surveillance requirements. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1985), the violation is listed below:

A. Technical Specifications (TS) 4.11.2.1.2, Table 4.11-2, Item 4, note 4, (iodine and particulate sample) requires sample collection to be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following'a reactor startup.

Contrary to the above, LER 2-86-009 reported that iodine and particulate sample collection was performed March 4, 1986, 43 hours4.976852e-4 days <br />0.0119 hours <br />7.109788e-5 weeks <br />1.63615e-5 months <br /> and 45 minutes after previous sample following a reactor startup on February 24, 1986-(Unit 2). i B. TS 4.2.1.2.1 requires that the indicated Axial Flux' Difference (AFD) shall be determined to be within its limits during POWER GENERATION above 15% of RATED THERMAL POWER by monitoring and logging the indicated AFD for each OPERABLE excore channel at least once per hour for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and at least once per 30 minutes thereafter, when the AFD Monitor Alarm is inoperable.

Contrary to the above, LER 2-86-006 reported that no AFD monitoring or logging was performed with the AFD monitor alarm inoperable during'the periods from 2:00 a.m. on February 20, 1986 to 1:15 p.m. on February 21, 1986 and from 12:00 midnight to 3:30 a.m. on February 26, 1986, while the reactor was at greater than 15% power.

C. TS 4.7.5.1 requires that each Control Room Ventilation System train shall be demonstrated OPERABLE at least once per 18 months by verifying that the heaters dissipate 5 i 1 kW'when tested in accordance with ANSI '

N510-1980.

Contrary to the above, LER 1-85-039 reported that no surveillance was performed until February 25, 1986, 27 months and 7 days after the previous surveillance (Unit 1).

D. TS'4.3.1.1 Table 4.3.1 requires each reactor trip system instrumentation channel demonstrated to be OPERABLE by performance of reactor trip system instrumentation surveillance channel _ calibration every 18 months for OP i Delta T and OP Delta P. )

Contrary to the above, LER 1-86-001-01 reported the following missed surveillances:

8605300689 860512 PDR O ADOCK 05000275 PM i

m

.1.__. .-,L_ _ . - . - . +- - - - , . - -

2

1. Reactor coolant temperature stannel 411/412 was calibrated on September 23, 1985, 35 months 12 days after previous calibration (Unit 1).

2. Reactor coolant temperature channel 431/432 was calibrated on April 22, 1985, 28 months 7 days after previous calibration (Unit 1).

3. Reactor coolant temperature channel 441/442 was calibrated on September 17, 1986, 34 months 27 days after previous calibration (Unit 1).

E. TS 4.3.2.1 Table 4.3.2 requires each Engineered Safety Feature Actuation System (ESFAS) instrumentation channel be demonstrated OPERABLE by performance of ESFAS instrumentation surveillance - channel calibration every 18 months for containment pressure.

Contrary to the above, LER 1-86-001-01 reported that containment pressure instrument, channel 935 was not calibrated until February 11, 1986, 24 months I day after the previous calibration (Unit 1).

F. TS 4.0.5 and ASME Section XI - IWV 3100 and 3522 requires each check valve, af ter installation and prior to service, to be tested by exercising it to the position required to fulfill its function.

Contrary to the above, LER 1-84-036-01 reported the following missed surveillances:

1. Unit 1 boron injection tank recirculation check VLV 8912 was not stroke tested to the fully closed position until January 14, 1986, 22 months 11 days after initial entry into Mode 3, when the valve was required to be operational.

2. Unit 2 boron injection tank recirculation check VLV 8912 was not stroke tested to the fully closed position until October 30, 1985, 3 ,

months 5 days after initial entry into Mode 3, when the valve was required to be operational.

G. TS 4.3.1.1 Table 4.3-1 Note (2) requires power range neutron flux reactor trip high setpoint instrumentation channel to be calibrated daily by performance of a heat balance when reactor power is above 15% of rated thermal power.

Contrary to the above, LER 1-86-002 reported the following missed surveillances:

1. With Unit 2 above 15% power, a heat balance was not performed until November 25, 1985, 54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> af ter previous heat balance.

2. With Unit I above 15% power, a heat balance was not performed until February 2, 1986, 48.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after previous heat balance.

H. TS 4.0.5 and ASME Section XI IWV 3100, 3300 and 3413 require that~ stroke l timing and position verification test be performed on power operated valves after installation and prior to service.

3 Contrary to the above, LER 2-85-023 reported that ten Unit 2 motor operated valves were not tested until October 3, 1985, 2 months and 9 days after initial entry into Mode 4, when the valves wer.e r.cquired to be operational.

I. TS 4.0.5 and ASME Section XI IWP 3230 and IWP 3400 require inservice testing of pumps every 3 months and the frequency doubled if test result deviations in the " alert range" are identified until the cause is determined and corrected.

Contrary to the above LER 1-85-037 reported the following missed surveillances:

1. Containment spray pump 1-2 was not tested until December 4, 1985, 92 days af ter previous test results identified an " alert rar.ge" deviation (Unit 1).

2. Containment spray pump 2-2 was not tested until December 5, 1985, 93 days after previous test results identified an " alert range" deviation (Unit 2).

This is a Severity Level IV Violation (Supplement 1).

Pursuant to 10 CFR 2.201, you are required to submit to this office within thirty days of the date of this Notice, a written statement or explanation in reply, including: (1) admission or denial of the alleged violations; (2) the reasons for the violations if admitted; (3) the corrective steps which have been taken and the results achieved; (4) corrective steps which will be taken to avoid further violatiour; and (5) the date when full compliance will be achieved.

MAY I 21986 Date wb-Marvin Mendonca, Chief Reactor Projects Section 1 l-