ML19263B304
| ML19263B304 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/16/1978 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19263B301 | List: |
| References | |
| 50-321-78-33, 50-366-78-41, NUDOCS 7901180011 | |
| Download: ML19263B304 (1) | |
Text
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APPENDIX A NOTICE OF VIOLATION Georgia Power Company License Nos. DPR-57 and NPF-5 Based on the results of the NRC inspection conducted on October 3-6, 1978, it appears that certain of your activities were not conducted in full compliance with NRC requirements as indicated below. These items have becn categorized as described in our correspondence to you dated December 31, 1974.
A.
Criterion XI, " Test Control" of Appendix B to 10 CFR 50 requires, in part, that test results be evaluated to assure that test requirements have been satisfied. Page 99 of revision 3 to the Start Up Manual (SUM),
in its implementation of this requirement and in its description of the operating functional checks to be done for paragraph V " System and Equipment Perf ormance" during heatup f rom ambient and 0 psig to rated temperature and pressore indicates that "the Operations Supervisor -
Unit 2 shall evaluate the testing to this point and indicate that in his judgement, the tests are adequate to continue operation and testings at higher power levels." Such evaluation is to be carried out and documented by sign-off of Appendix H to the SUM.
Contrary to the above requirement, operation and testing on Unit 2 up to 17% of rated power had continued in the absence of the Operations' Supervisor's concurrence with the adequacy of the testing for the
" Ambient and 0 psig to Rated Temperature and Pressure" plateau.
This item is an infraction.
B.
Technical Specifications 6.8.1 for Unit 1 requires, in part, that written procedures and administrative policies be established and implemented. Paragraph C.1 of page 2, revision 7 to plant procedure HNP-9, " Procedure Writing and Control," requires that "when a person using or reviewing a procedure detects an error or omission in the procedure, a Procedure Revision Request Form shall be initiated indicating a need to review the procedure."
Contrary to the above requirement, a Procedure Revision Request Form was not iniated f ollowing several usages on Unit 1 of HNP-9015, "APRM Calibration to Co e Thermal Power" subsequent to the August 25, 1978, establishment of a change in the 8X8 R fuel type peaking factor value indicated in HNP-9015.
This item is a deficiency.
7 9 0118 0 0l l
RII Rpt. No. 50-366/78-41 and 50-321/78-33 f.
Condensate collected in the off gas condenser is returned to the main condenser.
g.
Condensate collected in the water separator is returned to th" off gas condenser via a 6-inch loop seal, h.
The hydrogen analyzers obtain their sample via k-inch tubing downstream of the water separatcr prior to the holdup line i.
Condensate from the hydrogen analyzers goes to dirty radwaste via a 4-inch loop seal.
j.
The hydrogen analyzers are located overhead in a semi-enclosed room.
k.
There are no radiation, air activity, or hydrogen monitors in the following areas that contain off gas equipment:
Mechanical Vacuum Pump Room (RV to Atmosphere)
Hydrogen Analyzer Room Off-Gas Tunnel (From SJAE to recombiner room)
Preheater - Recombiner Room Off-Gas Condenser Room Cooler Condenser, Moisture Separator, Prefilter Room (Two monitor are located on the same level, but are outside the room).
A constant air monitor (AM) sampling room air is located on the naxt level up.
According to an HP representative, if. loop seal blows, the cam will initiate and alarm.
This may indicate an improperly balanced ventilation system (unresolved item 321/78-33-03).
1.
Dilution steam is continuously added to the off gas at the SJAE and moisture removed in off gas condenser downsteam of the recombiner.
m.
The off gas system lines are not uniquely identified to indicate that the line contains a potentially explosive gas.
The line na painted white indicating air or gas.
n.
The emergency procedure for handling off gas system conditions whit h threaten the integrity of the system has been written and is undergoing review.
GPC has requested an extention of the completion date identified in their reply to IEB 78-03 te December 31, 1978.
RII Rpt. No. 50-366/78-41,
and 50-321/78-33 during the inspection are discussed in paragraphs 6, 8 and 9 of this report.
4.
Exit Interview The inspectors met with licensee representatives (denoted in paragraph 1) on October 6, 1978 and reviewed the inspection scope and findings.
5.
Personnel Changes R. T. Nix, Maintenance Supervisor was promoted to Maintenance Superintendent.
s 6.
Off-Gas System - Unit 2 As a follow up on GPC's reply to IEB 78-03, Potential Explosive Gas Mixture Accumulation Associated with BWR Off-Gas Systems, a walkdown of the Unit 2 off sas system was made comparing the physical layout
~
to the drawint, ooking particular for loop seals, rupture disc, ability to bypa.
.he recombiner, ventilation of the area in which the equipment is
.cated, leak detection in the area, ie, hydrogen, air activity.
The following items were noted:
No rupture disc was found in the system nor were any specified a.
by design.
b.
Pipe caps were missing from vent lines in the recombiner rooms.
(redundant vent valves were closed) c.
There are two 19-foot loop seals in the cooler condenser moisture separator prefilter room that drain to clean radwaste.
The seals can be filled from outside the room.
One seal protects the volume of the holdup line to the isolation valve ahead of the cooler condenser.
The other seal protects the volume between the cooler condenser and the moisture separator.
Unless specifically noted later all other relief devices relieve,to other parts of the system.
d.
The volume between the Steam Jet Air Ejector (SVAE) and the recombiner is protected from overpressure by a safety valve that relieves back to the main condenser via a 3-inch line.
The preheater-recombiner volume is protected f rom overpressure c.
when isolated by a safety valve that relieves downstream of the isolation valve via a 2\\-inch line.
RII Rpt. No. 50-366/78-41 and 50-321/78-33 0% h
[/7 DETAILS I Prepared by:
- (
F. S. Cantrell, Piofec t Inspector Date Reactor Project Section No. 1 Reactor Operation and Nuclear Support Branch Dates of Inspection: October 3-6, 1978
//!/0 /7[
Reviewed by:
(
M H. C. Dance, Chief
/Date Reactor Projects Section No. 1 Reactor Operations and Nuclear Support Branch 1.
Persons Contacted hM. Manry, Plant Manager
- H.
C. Nix, Assistant Plant Manager
- S. X Baxley, Operating Superintendent hT. V. Greene, Superintendent. Engineering Services R. T. Nix, Maintenance Superintendent D. Smith, Counting Room Supervisor C. L. Coggin, Startup Test Coordinator
- G. E. Spell, Jr., Senior QA Field Representative
- W. B. Thigpen, QA Field Representative
- R. F. Rogers, IE Resident Inspector Discussions were held with operators, mechanics and technicians as appropriate concerning the subjects covered in this report.
hPresent at Exit Interview.
2.
Licensee Action on Previous Inspection Findings Noncomgliances Closed (321/77-24-01 and 321/78-13-01) - The Plant QA Department in addition to the responsible department now tracks reportable occur-rences to assure that the repcrt is is-
'd prior to the due date 3.
Unresolved Items Unresolved
(* cms are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance or deviations. Three unresolved itects disclosed