ML19210B819
| ML19210B819 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 11/02/1979 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| Shared Package | |
| ML19210B817 | List: |
| References | |
| NUDOCS 7911120493 | |
| Download: ML19210B819 (2) | |
Text
.
]
l
( '
NOTICE OF VIOLATION Vi ginia Electric anc Power Company License No. NPF-4 Nort
,'.nra Urit ~.
5asec cn the N inspection and investigation conductec Septemt>er 25 - October 5, 19~9, certain cf ycJr activities were apparently not conductu in full cv P iance wi n NE: require.erts as indicated below.
These items have been categorized as described ir. carresp ncence to you dated December 31, 1974.
A.
As recaired oy 13 CFR 50.59(b) and paragraph 14.5.2 of the Nuclear Power S aticn Quality Assurance Manual, records shall be maintained of changes tc :ne facility as described in the safety analysis report.
These recercs shall ir:lude written safety evaluations which provide the bases fcr determiring that tne changes do not involve unreviewed safety questions.
Centrary to the above, a one-inch licuid waste line, LW-81-152 (FSAR Figure 11.2.2-1) was found disconnected on September 25, 1979, at the flarged cenrection for restricting orifice R0-LW-104 with an elbow irstalled ir pla:e of the crifice.
The elbow was open to the auxiliary a iidinc atraschere and was a fics path for the release of radioactive gases ir tne e /e,t of Se tem::er 25, 1979.
This change was made to a s;. ster corocnent as describec in the safety analysis report without the reatirec evaluation.
Tris is an infra: tion.
A sinilar ite'n was brought to your attention in otr letter catec May 25, 1979.
E.
As recaired oy 1: CFR 50, Appendix a, Criterion 13, Instrumentation shall ce provided to a nitor variables and systems over their anticipated ranges far rarnal cperation, for anticipated operational occurrences, and fc r accident corditions as appropriate to assure adequate safety, including trase /ariables and systems that can affect the fission process, the irtegrity of the reactor core, the reactor coolant pressure boundary, and tre containcent anc its associated systems.
Appropriate controls shall be prcvided to traintain these variables and systems within prescrit'ed operatir; ranges. Also, as required by 10 CFR 50.59(b) and pararaph 12.5.2 cf tre NL: lear Power Station Quality Assurance Manual, records srall ce maintai ec of cnanges to the facility as described in the safety aralysis repar.. These records shall include written safety evaluations wricn provice the bases for cetermining that the changes do not involve urre/iewed safet cuestions.
Ccatrary to the abcVe, the control switch for the Volume Control Tank
('.:T) le/el cont ol valve, LCV-1115A was observed to be mechanically held
- c :ne V:T tosit on by me.sns of pencil and paper clip, on September 28 and Octcoer 1, 1979, negating the automatic level control functions of the valve as cescribec in he Unit 1 FSAR pages 9.3.4-7, 9.3.4-8, and 9.3.4-24.
This crarge in syste. oceration was also performed without the required evaluation.
1312 195 7 91112 0 %J
Appendix A Use of a paper clip and pencil fails to satisfy the definition of appropriate centrols to caintain variables and systems within prescribed operating ranges.
This is an infra ticn.
1312 196
,