ML17272A835: Difference between revisions
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| issue date = 02/04/1980 | | issue date = 02/04/1980 | ||
| title = Responds to NRC 791218 Ltr Re Violations Noted in IE Insp Rept 50-397/79-16.Corrective Actions:All Deficient Areas Were Inspected & Recapped & All Areas Were Cleaned & Capped | | title = Responds to NRC 791218 Ltr Re Violations Noted in IE Insp Rept 50-397/79-16.Corrective Actions:All Deficient Areas Were Inspected & Recapped & All Areas Were Cleaned & Capped | ||
| author name = | | author name = Renberger D | ||
| author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM | | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM | ||
| addressee name = | | addressee name = Spencer G | ||
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) | | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) | ||
| docket = 05000397 | | docket = 05000397 | ||
| Line 15: | Line 15: | ||
| page count = 9 | | page count = 9 | ||
}} | }} | ||
See also: [[ | See also: [[see also::IR 05000397/1979016]] | ||
=Text= | =Text= | ||
Revision as of 01:17, 19 June 2019
| ML17272A835 | |
| Person / Time | |
|---|---|
| Site: | Columbia |
| Issue date: | 02/04/1980 |
| From: | Renberger D WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Spencer G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML17272A834 | List: |
| References | |
| GO2-80-30, NUDOCS 8002280060 | |
| Download: ML17272A835 (9) | |
See also: IR 05000397/1979016
Text
Public Power Supply System A JOINT OPERATING AGENCY P.O.BOX 955 3000 GSO.WaS~IVOTON
WAY R>CRLANO.WiSRIVCrOrr
99352 PHONS (509)375 5000 Subject: WPPSS NUCLEAR PROJECT NO.2 DOCKET NO~50-397, CPPR-93 NRC INSPECTIO 22-25, 1979 REPORT NO.-397/79-1 Reference:
Letter G.S.Spencer to N.0.Strand, dated December 18, 1979 Dear Nr.Spencer: G02-80-30 February 4, 1980 G.S.Spencer, Chief Reactor Construction
and Engineering
Support Branch Nuclear Regulatory
Commission
Region V Suite 202, Walnut Creek Plaza 1900 N.California
Boulevard Walnut Creek, California
94596 J IIII::wL'II
g-', FFB 8 1'80 p'\"p, This is in response to your letter of December 18, 1979 (referenced
above), which documented
the results of the NRC inspection
conducted on October 22-25, 1979 of activities
authorized
by NRC Construction
Permit No.CPPR-93.This letter identified
three items of noncompliance
which were categorized
as infractions.
The specific NRC findingsas
stated in your letter, and the WPPSS responses are provided in Appendix A to this letter.If you have any questions or desire further information, please advise.Very truly yours, D.L.RENBERGER Assistant Director, Generation
and Technology
DLR/PJM/ln
Attachment;
As stated cc w/att: JH Blas-BdlR, NY HR Canter-88R, NY JR Lewis-BPA, Richland V Stello-Office of Inspection
8 Enforcement, Washington, D.C.JJ Verderber-BSR, NY
APPENDIX A Washington
Public Power Supply System P.O.Box 968 Richland, Washington
99352 Docket Number 50-397 Construction
Permit Number CPPR-93 NOTICE OF VIOLATION Based on the results of NRC inspections
conducted between October 22 and 25, 1979, it appears that certain of your activities
were not conducted in full compliance
with conditions
of your NRC facility license No.CPPR-93 as indicated below.A.10CFR 50, Appendix B, Criterion V, states in part, that"activities
affecting quality...shall
be accomplished
in accordance
with...instructions, procedures, or drawings..." Paragraph D.2.5 of the WPPSS guality Assurance Program documented
in the PSAR states in part, that"...all project contractors
for the nuclear related portions of the plant will be required to have a guality Assurance Program...the
program shall include the following items as...applicable
to the...construction
for which the contractor
is responsible." Paragraph D.2.5.5 states in part, that,"activity affecting quality...shall
be accomplished
in accordance
ijith...procedures...".
(1)Work procedure SP-2005-H2, of the Johnson Controls Inc., a site contractor, states"in part, that"all pipe and tube endings will be capped or otherwise closed at the end of each day."-Contrary to the above, on October 24, 1979, at the end of the work day, one process instrument
line on containment
no.72, two process instrument
lines on penetration
no.548, and four process instrument
lines on penetration
no.29 were found uncapped, exposing the internals of the reactor vessel.This is a repeat of previous NRC findings on February 27 and March 1, 1979.This is an infraction.
ACTION TO CORRECT DEFICIENCY
Corrective
Action Request No.220-1425 was initiated against the deficient penetration.
All deficient areas were inspected for cleanliness
and recapped.The 220 contractor
documented
the inspection
and rework on Inspection/Surveillance
Report Number 477, dated 11/5/79.
J p~4.
Appendix A (continued)
ACTION TO PREVENT RECURRENCE
Daily surveillances
were doubled by Johnson Controls in all areas in their custody.This activity began on October 29, 1979.Johnson Controls Project Manager issued a memo to all craft supervision
regarding the importance
of capping or sealing instrument
lines and penetrations.
This memo was issued and posted on the craft bulletin board November 15, 1979.Training sessions for craft and gA personnel were held between October 29 and December 12, 1979.Eleven classes were held.DATE OF FULL COMPLIANCE
Full compliance
was achieved December 15, 1979.(2)Fischbach/Lord
Electric Company procedure CP208 states under general maintenance
requirements: "covers, caps, plugs, and other closures shall be maintained
intact." This procedure goes on to state"dust coverings, shrouds, local sealing, heating methods and mechanical
cleaning shall be employed to keep the structure as clean and dry as possible." Contrary to the above, inspection
of instrument
racks H22 P026, H22 P027, H22 P005, and H22 P004, on October 24, 1979, revealed: (a)A heavy accumulation
of dust, dirt, and debris on all racks.(b)The racks were not.protected from adjacent construction
activities
and were used to store structural
bolts, structural
steel plates, and a gas pressure bottle cap.(c)On rack H22 P026, instruments
B22 N038A and B22 N036B had been removed without capping or otherwise protectinq
the opened tube ends leading to the instruments.
Likewise, on rack H22 P005, instruments
C34 N004C and B22 N026C had been removed without capping or otherwise protecting
the opened tube ends leading to the instruments.(d)Dirt and debris was evident during a visual inspection
of the inside of uncapped instrument
sensing lines on the above mentioned racks.This is an infraction.
ACTION TO CORRECT DEFICIENCY
All deficient equipment was cleaned and sealed or capped immediately.
0
Appendix A (continued)
ACTION TO PREVENT RECURRENCE
Surveillance
activities
have been increased to assure implementation
of maintenance
requirements
and protection
from construction
activities.
Corrective
Action Request No.218-1424, against the deficient maintenance
and cleanliness
activities, has been issued to the contractor.
A revised maintenance
procedure has been issued which clarifies maintenance
requirements
and establishes
specific time intervals for maintenance
performance.
Audits/surveillances
are being conducted to verify adequate corrective
action.In addition, for equipment under the cognizance
of Test and Startup, the Instrument
Test Guide will be revised to require performance
of System Lineup Test I-3 when removing or installing
any instruments
in the plant.This will assure cleanliness
and proper plugging/taping
of instrument
lines.DATE'OF FULL COMPLIANCE
Full compliance
was achieved on January 31, 1980.i.B.10CFR 50, Appendix B, Criterion III, requires in part,"measures shall be established
to assure that applicable
regulatory
requirements...are
correctly translated
into specifications, drawings, procedures, and instructions." FSAR table 3.2-1 lists reactor protective
system components
as guality Class I ("meets the quality assurance requirements
of 10CFR 50, Appendix B")and Seismic Category I.The PSAR paragraph 7.2.1.1,2"classification", further states..."The
Reactor protective
system is classified
as Safety Class 2, Seismic Catego'ry I, and guality Group B (Electrical
Safety Class IE)".Contrary to the above requi rements, on October 23, 1979, inspection
of the reactor protection
system (RPS)disclosed 4 turbine stop valve position switches (POS N006 A through D), and 8 pressure switches pro-viding RPS indication
of turbine governor valve fast closure (PS N005 A through D)were not specified and purchased to Electrical
Safety Class IE and Seismic Category I requirements.
This is an infraction.
ACTION TO CORRECT DEFICIENCY
An Engineering
change is being processed (Project Engineering
Directive (PED)No.218-E-2340)
to replace the existing instrumentation
with qualified instruments
or type tested existing instruments.
ap 0
Appendix A (continued)
In addition, the HNP-2 FSAR is being reviewed and will be revised to clarify the seismic classification, the quality group, and the quality class, as applicable, of the turbine generator inputs to the Reactor Protective
System.ACTION TO PREVENT RECURRENCE
1)NP-2 has a program in progress to identify all Class IE equipment and verify that adequate documentation
exists for each piece.The type of problem noted above will be identified
during this program, Corrective
action will be taken as appropriate.
DATE OF FULL COMPLIANCE
Full compliance
will be achieved by June 27, 1980.
0~1