ML19332E484

From kanterella
Jump to navigation Jump to search
Notice of Violation from Insp on 891002-06 & 16-20.Violation Noted:Failure of Turbine Driven Auxiliary Feedwater Pump Inservice Testing Procedures to Contain Acceptance Criteria for Comparison of Pump Differential Pressure
ML19332E484
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 11/22/1989
From: Gibson A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML19332E479 List:
References
50-348-89-26, 50-364-89-26, NUDOCS 8912070280
Download: ML19332E484 (2)


Text

.

"I t

+

+

u 3-3

)

ENCLOSURE 1 NOTICE OF VIOLATION Alabama Power Company-Docket Nos. 50-348, 50-364 Farley License Nos. NPF-2, NPF-8 During.the - Nuclear Regulatory Commission (NRC) inspection conducted on October 2-6, 1989 and October 16-20, 1989, violations of NRC requirements were identified.

In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1989), the violations are. listed below:-

-A.

Technical Specification 4.0.5 requires inservice testing of ASME Code Classes 1, 2,;and 3 pumps and valves in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. The licensee is committed Eto inservice testing in accordance with the 1983 Edition of the Code and Summer 1983 Addenda, a.

Section XI, Subsection IWP-3100 requires that each measured test quantity;be compared with the reference value of the same quantity.

Any deviations determined shall be compared with the limits given in Table IWP-3100-2 and the specified corrective action taken.

Contrary to the above, Unit I and Unit 2 turbine driven auxiliary feedwater pump inservice testing procedures FNP-1-STP-22.16 and FNP-2-STP-22.16 did not contain acceptance criteria for a comparison of pump differential pressure for the Table IWP-3100-2 High Values in the Alert Range.and Required Action-Range.

As such, differential pressure comparisons were not made-with the limits given in Table IWP-3100-2.

b.

Section. XI, Subsection IWV-3522 requires valves whose function is to prevent reversed flow to be tested in a manner that proves that the disk-travels to the seat promptly on cessation or reversal of flow.

Contrary to the above, the Unit 1 and Unit 2 turbine driven auxiliary feedwater. pump steam supply stop check valves HV3235A and HV3235B were not reverse flow tested in a manner that proves the disk travels to the seat on cessation or reversal of flow.

c.

Section XI, Subsection IWV-3522 requires valves whose function is to prevent reversed flow to be tested in a manner that proves that the disk travels to the seat promptly on cessation or reversal of flow.

Contrary to the above. the Unit 1 and Unit 2 motor driven auxiliary feedwater pump discharge check valves V002A and V002B were not reverse flow tested in a manner that proves the disk travels to the seat on cessation or reversal of flow.

8912070280 891122 PDR ADOCK 05000348 Q

PDC

4 y

Alabama Power. Company.

2 Docket Hos. 50-348, 50-364 Farley License Nos. NPF-2, NPF-8

'd.,

Section XI. Subsection IWV-3412 requires valves to be exercised to the position-required to fulfill their function.

' Subsection o,

9 IWV-3413(b). requires the stroke time of all power operated valves to be measured.

Contrary to' the-above,-Unit 1 and Unit 2 turbine driven auxiliary feedwater pump steam supply stop check valves HV3235A and HV3235B~ are-power operated valves which perform a function in the closed direction, and stroke times were not measured.

-This is a Severity Level IV violation (Supplement 1).

B..-

Technical Specification 4.4.5.1 requires each Power Operated Relief Valve (PORV) to be demonstrated - operable at least once per 18 months by

. performance of a channel-calibration and operating the valve through one L

cycle. of full travel.

A channel. calibration requires that the entire L

channel be calibrated, and shall include a channel functional test, in l-which an. injection: of a simulated signal into the sensor verifies operability, including, alarm and/or trip functions.

Contrary to the above..PORV channel calibration did not fully test the H,

automatic function contacts and associated wiring and circuitry. As such, the entire PORY channel was not calibrated.

ThisLis a Severity Level IV violation (Supplement I).

Pursuant to -the provisions of 10 CFR 2.201, Alabama Power Company is hereby

~

i required to submit a written statement or explanation-in response to Violation A only to.the Nuclear Regulatory Commission ATTN: Docnnent Control Desk, lr Washington, DC' 20555, with a copy to the Regional Administrator, Region II, and l

a copy to the NRC Resident Inspector, Farley, within 30 days of the date of the l

letter-transmitting this Notice.

This reply should be clearly marked as a "Re h violation:

.(1) ply to-a. Notice-of-Violation" and should include for eacadmission or denial of t L

l; admitted, (3)' the' corrective steps which have been taken and the results

' achieved, (4) the ' corrective steps which will be taken to avoid further J

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.

l FOR THE NUCLEAR REGULATORY COMMISSION Original Signed by Albert F. Gibson Albert F. Gibson, Director Division of Reactor Safety L

Dated at Atlanta, Georgia this22nd day of November 1989

.