ML20050F182
| ML20050F182 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/22/1982 |
| From: | Seidle W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20050F074 | List: |
| References | |
| 50-313-82-04, 50-313-82-4, 50-368-82-04, 50-368-82-4, NUDOCS 8204130348 | |
| Download: ML20050F182 (2) | |
Text
.
~,.
~
N'.
.'APPhNDIX.A y.
' Arkansas Pcwer and, Light / Company
'.-~
}
Dockets: 50-313
~
. Arkansas Nuclear Ons,-Units1 and 2 50-368 Licenses:
DPR-51 e
], -j c
^;-
NPF-6 s.
- ,3.
',.. /: ^
~
Based on the results of an NRC, inspection conducted during the period
- of. February 1-28,1982 and in.accordance with the Interim Enforcement t
policy 45 FR 66754 (October 7, 1980), the foll,owing violations were identified:
3
.nL K
1.
Seismic Support Pipe Strap Missing s
~
/i Criterion V to Apperidix B cf 10 CFR Part 50 states':
" Activities affect-ing quality chall be. prescribed by documented instructions, procedures, or drawings,'of a-type. appropriate to' the ciicumstances and shall be
'~ ~
^
~
~,
accomplished in accordance with,these instructions, procedures, or
/
'e drawings.*,
Plant Dcawing 00-208-H shoi.is the location of nine seismic supports for line number GBD-22 and refers to Plant Drawing M-1021,. Sheet 1, for a
-sketch of the supports.
Line number CDD-22 is.in the starting air system for the Unit 1, number 2, Emergency Diesel Generator. This line is included in the Unit 1 Q-List. _ Plant Drawing,M-1021, Sheet 1, shows the required configuration for the seismic supports for line GBD-22
'~
and notes that the pipe strap is:WP.lded,or bolted to the pipe support.
Contrary to the above, on February 8,1982, ' ne of the required pipe o
straps on line GBD-22 was observed by the NRC inspector to be missing.
This is a Severity Level IV Violation. 'TSupplemant I.D.3) (313/8204-01) 2.
_ Manual Valves Locked in Wrong Position
~
Unit 1 Technical Specification 6.8.l' req ~uifres that, " Written procedures N
shall be established, implemented, and maintained covering... a.
The C
applicable procedures recommended in Appendi.v'A' of Regulatory Guide 1. 33.... "
- f Operating Procedure 1104.02, " Makeup and Purification System Operations,"
l' has been established in accordance with this Technical Specification.
Attachment A of Ope:ating Procedure 1104.02' requires that manual valves MU-23 and MU-24 be locked closed and locked open, respectively, when the H-,
"C"MakeupPumpisinEngineeredSafeguard(ES) Standby. These valves are in the discharge crossconnect line between the "B" and "C" Makeup Pumps.
8204130348 820322 PDR ADOCK 05000313 PDR G
,g y
~
t..
,s 7
s-N
('+i
++
Contrary to the above, on. February 4,1932, with the "C" Makeup Pump s
in ES Standby, the NRC' inspector found that ganual valve MU-23 wee locked open and MU-24 was'Yccked cidsed. T-
. st t
This is a Severity Levet V 'liclation.
(Supple'nent I.E) (313/8204-02)'
c
- , ' 3 3.
Operator Training in Fire Detection System Design Change k
Paragraph 3 of Appendix A, "RequalificatiNn Pro rams for Licensed Oper-ators of Production and Utilization Facilities,to 10 CFR'55 states, in part:
"The requalificatiori program shall. include on-the-job train--
Each licon' sed;ol erator and senior operator is. cog-ing so that:... c.
i nizant of facility design chariges, procedure changes, and facility-s license changes."
Contrary to the above, on February 9,1982, the NRC inspector deter-mined that an entire shift of Unit 2,lic6nsed operators, consisting of a senior reactor operator (shift' supervisor) and two reactor' operators,
~
were unaware of the current ' status and sco'pe of and had not received training on the facility design change that modifies the Unit 2 fire detectioninstrumentationsystem(desi$nchangepackage 79-2082).
This system is required by UniEs2. Technical Specification 3.3.3.8.
Additionally, these licensed operatcrs'had not receivec\\instNetion on the new plant procedure (Procedure 2203:09) governing.tHe operation of the modified fire detection system ^and were not aware of the procedure's existence. This facility design ~ chat;ge' began' during September 1980,. s 1
and the majority of the work was ~ completed by July 1981.
The new plant procedure for this design changeswas issued in riovember 1981.
This is a Severity Level IV Violation.
(Supplement I.D.3)-(368/8204-01) s Pursuant to the provisions of 10 CFR 2.201., ArkansiciPower and LightlCompany -
is hereby required to submit to this office within 30 days of the date c('tnis Notice, a written statement or explanationiin reply, including (l)Jthe cdrrec-tive steps which have been taken a'nd the ye'sults achieved; (2)'correctiVc i steps which will be taken to avc-id further violation;; and (3)~the ddte when full compliance will be achieved. ilnder the authorf ty of SecticW182 of the Atomic Energy Act of 1954, as amended, thist resporoe shall be ' submitted under oath or affirmation.
Consideration may be gi.ver. to' extending,your response time for good cause shown.
s
)
~
i
~
s
'l f
sk -
Date:
March 22, 1982
-q-
'W., C. SeMle, Chief Reactor Pfoject Br'anch 2 3
x s
t
(
N *
'g n\\
' - +_
\\
n\\
a L -
C
.,