ML18033B140
| ML18033B140 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/18/1990 |
| From: | Wilson B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18033B139 | List: |
| References | |
| 50-260-89-53, NUDOCS 9001300146 | |
| Download: ML18033B140 (5) | |
Text
ENCLOSURE 1
NOTICE OF VIOLATION Tennessee Valley Authority Browns Ferry 2
Docket Nos.
50-260 License Nos.
DPR-52 During the Nuclear Regulatory Commission (NRC) inspection conducted on November 15, -
December 18,
- 1989, two viola.ions of NRC requirements were identified.
The first violation involved failure to comply with plant procedures for operator response.
The second violation was for failure to initiate Condition Adverse
.o qua',ity Repo'-s (CA(}Rs) for tes deficiencies when "repair", and "accept as is" actions were considered.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C ( 1989),
the violations are )isted below:
A.
Technical Specification Sec-.ion 6.8. 1. I.a requires that written procedures shall be established.
implemented, and maintained covering system operations.
Plant Y<anaoers Instruction 12, 12, Conduct o>>
Operations, requi res that the operator a-he controls and the immedia e
supervisor must be continuously alert zo plant conditions and ongoing activities affecting plant operations, including conditions external to the plant, such as grid stability, me-.eoroiogicai condi ions, and change in suppor-.
equipment status; operational occur, ences should be an:icipa ed:
alarms and off-normal conditions should be promptly responded to; and prob!ems affecting reactor operations should be corrected in a timely fashion.
Contrary to the
- above, 1989, the water level i
the ventilation system This resulted when the room personnel.
between 4:00 a.m.
and 5:30 a.m.
on.December 2,
n Un't 2
Snent Fuel Storage Pool overflowed intro and leahed onto areas of the reactor building.
alarm was not adequately acted upon by control This violation is similar to a violation identified in NRC inspection
. report 89-35.
This is a Severity Level IV Violation (Supplement I) and is applicable to Unit 2.
B.
10 CFR-50, Appendix B, Criterion XVI requires that measures shall 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.
0 The licensee's Nuclear equality Assurance Manual (NgAYi), Par I, Section 2.16, Corrective
- Action, requires that test deficiencies
- which, by evaluation, indicate that the item does not comply with the lice".,se
Tennessee Valley Authority.
Browns Ferry 2
2.
Docket Nos.
50-260 License Nos.
DPR-52 design
- basis, or which affect plant technical specifications, shall be
- placed, on a
CAQR if "accepted-as-is" or "repair" actions are being considered.
Site Directors Standard Practice
- 3. 13, Corrective Action, implements the NQAM requirements.
Contrary to the
- above, the following two examples of test deficiencies which involved "repair" and "accept-as-is" activities were not addressed as conditions adverse to quality.
During performance of Restart Test Procedure 2-BFN-RTP-031A, Control Bay Heating Ventilation and Air.Conditioning, the Unit 1
and Unit 2 Control Bay chill water'lows failed to meet the acceptance criteria.
The deficiencies were documented by Test Exception TE-07.
The test exception was closed with a
repair activity, through temporary modification TACF 0-88-002-031, without initiation of a
CAQR.
2)
During performance of post modification test PMT-161, after installation'f new shutdown board room emergency cooling units for shutdown board rooms C
8 D,
the cooling units tripped prior to obtaining-. the required. test data for the cooling capacity calculations.
Because of this, the acceptance criteria could not be verified.
Test exception EN-8 was written and dispositioned as acceptable without meeting the acceptance, criteria because the test would require'dditional heat load to be added in the room.
Although previous testing of the old cooling units had been conducted using Technical Instruction TI-81, Shutdown Board Room Emergency Cooling System Performance Check, this test exception was dispositioned wit',hout issuance of a
CAQR for an "accept as is" condition.
The shutdown electrical boards are required to be
'operable by plant Technical Specifications 3.9.A, since they provide electrical power to equipment used to mitigate accidents.
This is a Severity Level IV violation (Supplement-I) and is applicable to Unit 2.
Pursuant to the provisions of 10 CFR 2 '01, you are hereby required to submit a wr'itten statement or explanation to the Nuclear Regulatory Commission, ATTN:
Document Control
- Desk, Washington, DC
- 20555, with a
copy to the Associate Director for Special
- Projects, Office of Nuclear Reactor Regulation, and a
copy to the NRC Resident
'Inspector,. Browns Ferry, 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:
( 1) admission or denial of the violation, (2) the reason for the violation if admitted, (3) the
Tennessee Valley Autnority Browns Ferry 2
Docket Nos.
50-'260 License Nos.
DPR-52 corrective steps which have been
-aken and the results achieved.
(4) the corrective steps which will be taken :o 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.
FOR THE NUCLEAR REGULATORY COllN!SSION for Inspection Programs'VA Projec-s Division Office of Nuclear Reactor Regu)ation Dated at Atlanta, Georgia this lf-'"day of'January 1990
0 0