IR 05000321/1980044
| ML20003D422 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/30/1981 |
| From: | Quick D, Whitener H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20003D395 | List: |
| References | |
| 50-321-80-44, 50-366-80-44, NUDOCS 8103270096 | |
| Download: ML20003D422 (5) | |
Text
.
.
,
i A
R Rf Go'%
'
UNITED STATES 5. !.h,,,[7 j%
! "'A NUCLEAR REGULATORY COMMISSION
! $
REGION 11 o,
4[g8 101 MARIETT A ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303
% ' % / g"
w
...+
Report Nos. 50-321/80-44 and 50-36E/80-?4 Licensee: Georgia Power Company 270 Peachtree Street Atlanta, GA 30303 Facility Name: Hatch Unit I and Unit 2 Docket Nos. 50-321 and 50-366 License Nos. DPR-57 and NPF-5 Inspection at plant site near Eaxley, GA r.) I
/
l)w
_....m
<
inspector
%, 4.
/ 4) 't, ; j,~ e.y
, c-'
s/
H.'L. wnitener Date signeo Approved by b
[
uo
_/dC ~ f[/
0. R. Quick, 'Section Chief, Date Signed RCNS Branch SUMMARY Inspection on November 18-21, 1930 Areas Inspected This routine, announced inspection involved 30 inspector-hours on site in the areas of followup inspection of outstanding items, observation of installed supports and restraints, observation nf surveillance testing, and review of test results.
Results Of the four areas inspected, no items of noncomoliance or deviations were identified in three areas; one item of noncompliance was found in one arec (inadequate control of safety related maintenance activity).
.,
8103 27 o ogg
.
.
.
.
C-ir.-s
.n-
1.
Persons Centacted Licensee Employees
- C. T. Mccre, Assistant Plan *. Manager T. Green, Assistant Plant Manager
- C, L. Coggins, Superintendent of Engineering Services
- R. Nix, Superintendent of Maintenance
- J. L. Dawson, Maintenance Supervisor R. Lock, Engineering Superviser H. W. Dyer, Operations Supervisor
- C R.' Miles, QA Field Sucervi ser
- C. E. Selficwer, CA Site Supervisor
"T Elton, Senior Plant Engineer
"W. B. Thigpen, Senior QA Fieic Representacive
- R. D. Hiiceroranc, Maintenance Foreman J. Newman, Mechanical Maincenance Foreman Other licensee employees included leak rate and snubber test perscnnel.
NRC Resident Inspector
- R. F. Rogers, Senicr Resident Inspector
- Attended exit interview 2.
Exit-Interview The' inspection scope and findings were surmarized en November 21, 1950 with those persons indicated in paragraph 1 above.
3.
Licensee Action en Previous Inspeccion Findings Not inspected, i
4.
Unresolved Items
~
~
' Unresolved items are matters about which =cre information is required to
determine whether-they are. acceptable or may involve noncompliance or deviations.
New unresolved items. identified during this inspection are discussed in paragraph 5.
5.
Inspection of Outstanding Items 1The inspector reviewed the status of outstanding items related to leak' rate testing and piping support and restraint systems to ensure that the current listing of: cutstanding items is correct. Additionally, licensee action to complete commitments en several cutstanding items was reviewed'as follows:
-a.
(Closed) IES 78-09 concerned the development of procedures for closure
.of centainment hatches. The procedures are to contain requirements.
.
.
proven adequate by Type A leak rate tests. The license has developed procedures which incorporate specifications and instructions demon-strated to be adequate during pravious integrated leak rata tests, as follows:
(1) HNP-1-6705 (Revision 4) and HNP-2-6705 (Revision 2), ":nstallation and Renoval of Dryvell Head, Access Hatches and Equipment Hatches."
(2) HNP-1-6706 and HNP-2-6706, " Torus and Control Red Drive Manway:>
Installation and Removal."
The inspector concluded that these crocedures generally meet the intent of the bulletin but could be improved by the inclusion of clarifying statements to certain instrt.ctions and additional specific information These matters were discussed with licensee management personnel who concurred with the inspector's findings and agreed to revise the 6705 procedures.
The revision will include but is not limited to the following:
(1)' Maximum torque values.not to be exceeded without further engineer-ing evaluation. Minimum values are specified.
(2) Drywell head gasket to be used by material or part number in that Unit 1 and Unit 2 gaskets are different materials.
(3)
Inspection controls and QC hold points applicable in the event a head gasket is to be reused.
(4) Specific guidance for determining acceptability of the head torquing process. The term" approximate correlation" now used
.
in the procedure is dif ficult to evaluate.
b.
(Closed) IEC 78-07 concerned damaged components to a Bergen Patterson 25000 series test stand.
This matter was not applicable when issued.
However the licensee has recently obtained a 25000 series test stand, in'e i1censee stated that the concerns of IEC 73-07 w ll be reviewed and i
addressed as necessary within 30 days. ' The inspector opened inspector followup item (321/366-80-44-02). for the purpose of tracking licensee
-
action in this matter.
~
c.
(Closed) IFI 321/78-28-03 and 366/78-36-04. concerned verification af ethylene propylene seal material in hydraulic sn'ubbers' or the deter-mination of the lifetime. for the type of' seal material in use.
~
Documentation 'was available which indicated that attempts to obtain
- verification of seal material from vendors had.been made. E-system was the only vendor response received.
Licensee management was certain
-
that ethylene propolene material had been installed in all other Unit 1
.
. hydraulic. snubbers' in 1976.and stated that a search would be performed
_
'to produce the needed: material documentation for both Unit 1 and Unit'2. The NRC will be f rtformed of these findings within 30 days.
.
La
)
-
.
,
.
The inspector clcsed the IFI item and elevated this mattet to unresolved items 321/80-44-03 for Unit 1 and 366/S0-44-03 for Unit 2.
d.
(Closed) IFI 321/79-25-03 concerned the reinspection of safety-related snubbers as a result of some potential problems icentified during an IE inspection of July 23-27, 1979. The inspectcr reviewed the maintenance request and selected data for the required inspection which was per-formed on August 10, 1979 for non-accessible snubbers and August 12 for accessible snubbers.
This item is closed.
e.
(Closed)
IFI 321/80-21-01 and 366/80-21-01 concerned the performance of a random inspection of accessible mecnanical snubbers and develop-ment of a mechnical snchbar inspecticn ar.d functional cnack prccedure.
The procedure, HNP-6956, was approved on June 3, 1950.
Maintenance requests were issued on May 28 and June 3 to implement the inspection.
Inspection results were submitted to the NRC.
This item is closed.
f.
(0 pen) IFI 321/80-21-02 and 366/80-21-02 concerned the replacement of International Nuclear Safeguards mechanical snubbers with other snubbers.
The inspector determined that replacement is in progress but not yet complete.
This item remains open.
6.
Observation of Tests The inspector witnessed surveillance testing to determine that appropriate procedures were available and followed. The tests observed were as follows:
a.
Containment Atmospheric Control System The inspector verified correct valve alignment, venting and test pressure for the local-leak rate testing of T48-F333A.
Some packing leakage was observed in the test connection and block valves.
The packing leaks were corrected ~. and the isolation valve successfully retested. -The inspector had no questions on this test.
si b.
Hydraulic Snubber The inspector observed a functional test of SSA2, a 50 kip E-System hydraulic snubber. The snubber exhibited erratic behavior outside the acceptance range.
This ' matter was discussed with licensee personnel
.who stated that the cause would be determined. Other E-System snubbers will be tested if appropriate. This matter was _ identified for followup inspection as IFI 366/80-44-0 i
'
-
.
,
,
.
In addition to witnessing the above tests, the inspector toured the drywell area to inscect installed pipe supports and restraints.
No significant problems were identified on this tour.
7.
Review of Test Results The inspector reviewed selected data from snubber inspections of August 1979 and June 1980. With one except. ion no problems were identified in the test results.
The problem identified concerned a Unit 1 leaking snubber 1E 41-HPSE-H13 on the HPCI system. Mainten-'ce request MR 1-S0-3t24 was initiated on June 26, 1980 and comoleted by the replacement of the leaking snubber on July 1, 1980.
The inspector reviewed this matter witn licensee personnel and determined that conditicns were as follows:
a.
MR 1-80-3424 issuea June 26 icentifiec tne leaking snuoter.
b.
Above MR was signed off by the operations su;:e rvi sor on June 26, indicating maintenance as the responsible department.
c.
Maintenance Supervisor reviewed the MR on June 29.
d.
MR received by maintenance foreman for implementation July 1 and completed July 1.
e.
Snubber 1E41-HPSE-H13 tested July 1 and did not meet bleed rate specified by procedure and was replaced July 1.
f.
Snubber operability is required for all operation modes except refueling and cold shutdown.
In the period June 26 - July 1, the reactor was brought from hot standby to low power critical.
Itchnical Specification 6.8.1 requires that maintenace activity on safety-related equipment be controlled. In that four days elapsed from the time a potentially inoperable snubber was identified until the snubber was removed.ind tested the irspector concluded that the management controls did-not adequately control the timeliness of maintenance activity.
The licensee was informed at the exit interview that he was in violation of Technical
"
Specification 6.8.1.
This matter was identified for foilow up as MI/80-44-01.
.
-
-