ML19351F693
| ML19351F693 | |
| Person / Time | |
|---|---|
| Site: | Humboldt Bay |
| Issue date: | 01/09/1974 |
| From: | Searls F PACIFIC GAS & ELECTRIC CO. |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| IEB-73-06, IEB-73-6, NUDOCS 8102180309 | |
| Download: ML19351F693 (3) | |
Text
..
P.A.C I F I C GAS AND E LE C T RIC C O M PANY bbWb l
77 BE ALE S TREET S A N F R A N CISCO, C ALIFOR NI A 94106 * (415) 781 4211 P R E D E RIC K T. S E A R Ls
.a.a.
January 9, 1974
- 07. :7.*r::
oww c.
omaissEv 00'O."
,u..me
.m
=~.*.:.~0.
9 r.,o,
- =. c =..: -
..m..
..m.......
q, A
==.ver-e.....tv......
.6e......e..u..
,u
. ~......
4 Ant 111374 h N5,Eh,'*-
'"1" ' *." 'C " '
LEG 03 V y
n=g;,n.,,
t Mr. R. H. Engelken, Director DIR.0E E
,.C.' J =
- t*
s l
Directorate of Regulatory Operations d OPERAT1314 t,;.*.' * : --
Region V Y
E~=,,4,f,U,0 _
U. S. Atomic Energy Commission
' f I i 'g '
' O'.':.".- - "
P. O. Box 1515 Berkeley, California 94701 Re:
Docket No. 50-133 License No. DPR-7 Humboldt Bay Power Plant
Dear Mr. Engelken:
Your letter dated November 26, 1973 requested that a review be conducted concerning specific procedures, management controls and licensed operator performance as specified in the Directorate of Regu-latory Operations Bulletin No. 73-6 titled, " Inadvertent criticality in a Boiling Water Reactor."
A summary of the status of each item identified in each paragraph and subparagraph of the aforementioned bulletin is given below.
1.
Procedural Review a.
Control Rod Drive Operating and Testing Procedures (1)
A review of all control rod drive operating and testing i
procedures has been completed.
Approved procedures exist l
for all normal control rod drive performance tests.
When special tests are required, procedures are developed, re-l viewed and approved prior to conducting the tests.
An approved procedure also exists for all normal operations involving the control rod drive system.
As a result of your letter, this procedure was reviewed.
A revision of the procedure involving the addition of specific procedures for two normal operating functions not covered in detail in the present procedure has been prepared.
The revised pro-cedure will be approved and issued prior to February 1,1974.
Bioa/r636 i
-Mr. R. H. Engelken 2
January 9, 1974 The plant emergency procedures are being revised to implement the recommendations of ANSI N 18.7-1972 end Safety Guide 33.
Two of these procedures in--
volve potential control rod system malfunctions.
Review and approval of these procedures should be com'leted by February 1, 1974.
(2)
All control rod drive testing procedures were re-viewed and revised as necessary to include pre-requisites relating to the testing of associated interlocks and protection features prior to conduct-ing tests involving significant rod movements during regularly scheduled refueling outages.
(3)
All control rod drive procedures were reviewed and were found to contain sufficient prerequisites and instructions to demonstrate compliance with require-ments of the Technical Specifications and with design bases.
b.
Bypass Installation Procedures At present a jumper status log is maintained by the Instrument Foreman and the Control Operator is notified by the Instrument Foreman of all jumpers which are installed or removed from plant equipment.
However, no written procedure exists at present to cover the use of jumpers.
A Steam Ger,eration Department Nuclear Plant Administrative Procedure entitled
" Jumper Control", which will be followed in the operation of all the Company's nuclear plants, and an implementing procedure for the Humboldt Bay Power Plant describing in detail the use of the jumper status log have recently been prepared as part of the Company's overall operational quality assurance program.
These two procedures were placed in ef-fect on January 9, 1974.
c.
Radiation Protection Procedures Access control and accountability are regulated by the exist-ing Radiation Control Standard and Radiation Control Procedure entitled " Control of Access."
The most recent review of this standard and procedure occurred in March 1973.
The procedure requires that all personnel be logged "in" and "out" of the controlled area of the plant and describes the evacuation procedures to be followed upon the sounding of the various evacuation alarms.
These procedures also describe the use of the Special Work Permit (SWP) and Radiation Work Permits (RWP).
All work in the controlled area must be authorized by one of these permits.
Dir. R. H. Engelken 3
January 9, 1974 d.
Shift Transi+, ion Procedures The practices followed at the Humboldt Bay Power Plant for shift turnover are based upon the requirements of the Com-pany's " General Operating Orders for Steam Electric Power Plants."
In order to consolidate these requirements as they relate to nuclear power plants, a Steam Generation Department Nuclear Plant Administrative Procedure entitled
" Relieving the Watch", has been prepared as part of the company's overall operational quality assurance program.
This procedure, which includes requirements for communicating to the incoming operator a full report on station conditions, was placed in effect on January 9, 1974.
2.
Management Controls At the present time management controls are in effect which re-quire the review cf temporary circuitry changes and temporary off-normal plant conditions.
This review is accomplished by the plant's On-site Review Committee, which is composed of qualified plant supervisory personnel including the Plant Superintendent and those supervisors responsible for the opera-tion, maintenance and technical activities of the plant.
The committee is required by charter to provide a review of any change or test proposed by the plant organization and periodically to review plant operating cverience.
3.
Licensed Operator Performance The company in its letter to the AEC dated December 14, 1973 described the requalification program for licensed operators of the Humboldt Bay Power Plant Unit No. 3.
This requalifica-tion program, which was initiated December 17, 1973, is based upon the requirement of Appendix A to 10 CFR 55.
This program requires among other things that each operator annually demon-strate a satisfactory understandincj of Unit No. 3 operating procedures, and also that he be r. quired to review all abnormal and emergency procedures at least once every six conths.
Very truly yours,
.