IR 05000416/1981050
| ML20033D207 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/06/1981 |
| From: | Blake J, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20033D206 | List: |
| References | |
| 50-416-81-50, 50-417-81-22, IEB-80-07, IEB-80-21, IEB-80-7, NUDOCS 8112070380 | |
| Download: ML20033D207 (6) | |
Text
7-
-
-
.
_ _ _ _ _
~
-.
....
o, UNITED STATES
- 8 NUCLEAR REGULATORY COMMISSION o
- d E
REGION 11
'
o 101 MARIETTA ST., N.W., SulTE 3100 k~.....o ATLANTA, GEORGIA 30303
,
Report Nos.- 50-416/81-50 and 50-417/81-22 Licensee:
Mississippi Power and Light Company P. O. Box 1640 Jackson, MS 39205 Facility Name:
Grand Gulf Nuclear Station Docket Nos. 50-416 and 50-417 License Nos. CPPR-118 and CPPR-119 Inspection at Gr ulf site near Port Gibson, MS
//
5/
Inspector:
f v
J. J / T 'ke Dat Signed Approved by:
bd(
// [
/
A. R. Herdt, Section Chief Gate' Signed Engineering Inspection Branch Engineering and Technical: Inspection Division-SUMMARY Inspection on October 27-30, 1981 Areas Inspected -
This routine, unannounced inspection involved 26 inspector-hours onisite in the areas of Licensee Identified Items (50.55(e)); Previous Inspection Findings;
.
Safety Related Structures (Structural Steel ~and. Supports); Reactor - Coolant
-
Pressure Boundary Piping;. Reactor Vessel Internals; Safety Related-Components; Containment (Steel Structures and. Supports);- and IE Bulletins.
Results
Of the seven areas inspected, no. violations or deviations were-identified.
..
8112070380 8'11110 PDR ADOCK 05000416
- PDR.
-
..
,_ _
,
.-
,
^
~'
L -.'_
t
_.
L'
L
-
,
.l
..
h..
.
!
REPORT DETAILS 1.
Persons Contacted Licensee Employees
- G. B. Rogers, Jr., Site Manager
- J. W. Yelverton, QA Supervisor
- S. F. Tanner, QA Coordinator D. D. Little, QA Representative Other licensee employees contacted inclui.d several construction craftsmen,.
QC technicians, and office personnel.
NRC Resident Inspector A. Wagner, Senior Resident Inspectcr
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on October 30, 1981 with those persons indicated-in paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings (Closed) Violation '(50-416/81-24-01) Drawing Control.
MP&L letter No.
AECM-81/320 dated 8/24/81 has been' reviewed and determined to be acceptable by. Region-II. The inspector held discussions with MP&L QA representatives and examined the corrective actions as ' stated in the letter. of response.
The inspector concluded that MP&L' had determined the full extent of 'the subject noncompliance,' performed the.necessary survey.and follow-up actions to correct;the present cunditions and developed the necessary corrective actions to' preclude recurrence of similar circumstances.
The. corrective actions identified in the ~ letter of response have been implemented.
4.
Unresolved items
' Unresolved items'were not identified during this inspection.
1'
5.. Licensee Identified. Items (50.55(e))
The inspector reviewe'd the licensee's-activities and QA records assoitated.
?!
~
with. items rep'orted in.accordance with 10 CFR 50.55(e). The, items reviewed
.
were as follows:
o
- (Closed -. Unit 1;. 0 pen - Unit 2)1(CDR 81-10)1 Pos' ible MSV. Drain Line i
.a.
s
,
0verpressurization 1(PRD: 81/10). This item was originally-' reported toj NRC on February 18,-1981, and the following; written reports were -
m r
,
.
4-
- - - -
.
.
-
-
-
g
=
.-
.
forwarcac: AECF81/113 of March 20, 1981; and Finai Report AECM-81/356 of September 16, 1981. The inspector reviewed these reports and the supporting documentation.
The licensee has replaced the affected piping in Unit 1, but as Unit 2 is inactive, no corrective. action has been taken. This item is closed for Unit 1 but will remain open' for'
Unit 2-until the design drawings for the affected piping are changed, b.
(Closed) (50-416/81-02-01, ~50-417/81-01-01) Undersized Socket -Welds (PRD 80/43). This item was reported to NRC-on July 18, 1980 and'the following written reports provided: AECM-80/190'on August 15, 1980; AECM-81/58 on. February 4, 1981; and Final Report AECM-81/323 on September 16, 1981.
The inspector reviewed the written reports and supporting documentation which showed that allof the Unit 1 undersized socket welds have been identified and repaired and all of the Unit 2 undersized socket welds have - been identified, documented and will be repaired when Unit 2 returns to active construction status, c.
(Closed) (50-416/80-23-06, 50-417/80-14-06) Standby Service Water Basin Fan Bearings Failed (PRD 80/52). This item was originally reported to NRC on August 26, 1980. Written reports submitted were as follows:
AECM-80/232 of September 26,.1980; AECM-81/22 of ' January 6,.1981; AECM-81/152 of April 22,-1981; and Final. Report No. AECC-81/167 - of September 23, 1981.
The inspector reviewed these reports L and the supporting documentation which show that the - bearings -- have been '
replaced.
d.
(Closed) (CDR-80-63) Tuttle and Bailey Type' VLK Air Extractors (PR0 80/63).
This item was originally reported ' to NRC' by itelecon on-
~
.0ctober 15, 1980.. Written-reports. submitted were AECM-80/285 _ on November 14, 1980; AECM-81/101 on. March 12, 1981; and the Final Report AECM-81/233~on July 2, 1981. Thefinspector reviewed these reports and supporting documentation which show that type VLK extractors-bave been~
eliminated from every place except the' control room'HVAC. - The control:
room extractor s have.been modified by the addition ofisupport' straps.
~
- This item.is closed.
'
- e.
(Closed) (CDR-81-36) Incorrent ' Beam Sizes for. Cable Tray Supports-
=(PRD-81/36)
This' item was reported to NRC. on September 3, ~1981. by telecon with a-. final written report'AECM-81/376 dated 10ctober:1,11981.
The inspector reviewed the written report' and the isupporting'documen-
-
_t a t i o n.~ ; The supporting ~ documents revealed that - this ' problem. was disco'vered in late 1977 withtcorrective action complete.infearly 1978.
The probbm was' originally determined:to be not" reportable Lunder,the c
~'
reportability; gbidance in ef fectJat -theisite.at:that timec Re-review ofrthe_ item under current-. guidelines showed'the? item to be-reportable.
- lIn that the corrective action _ is complete,.this-item is closed.
(Closed)} (50-4' 6/80-23-14, CDR 80-57) HVAC Automatic! Air Da_mpers-(PRD
~
f.
80/57). This problem _was;1dentified to NRC by.teleconlon September 12-
-1980.- Written reports consisted of AECM-80/254 dat.d Octobe'ry13,1980; x
,
i AECM-81/41'date'd Januaryr23i 1981;1AECM-81/270 dated' July.29,11981;"and?
.
.
-
$
-
Y q.
g
.
.
.
.
_....
r' 4
_t
,
,
.
.-
.
~.
.
.
.
.
Final Report AECM-81/412 dated October 19, 1981. The problem concerned broken tack welds on the dampers.
The supporting documentation indicates that the cause of the broken tack welds was either improper welding by the vendor (licensee determination) or misha'ndling after receipt (vendor determination).
At any rate. - the problem was solved by the addition of a thru bolt mechanical connection to replace the tack weld. This item is closed.
6.
Licensee Identified Items - Not Reportable The-inspector reviewed the documentation. packages for two problems which had reached the final reportability review stage and had been determined to be not reportable under 10 CFR 50.55(e). The items reviewed were as follows:
,
a.
PRD 80/02, Defective Elbow in Control Rod Drive Hydraulic System b.
PRD 81/29, Temp Flex Penetration Bellows Assemb13 The inspector reviewed the documentation for both items and could find no
+
fault with the rationale that neither item was reportaole under - 10 CFR 50.55(e).
There were no violations or deviations in this area of the inspection.
t 7.
IE Bulletins The inspector reviewed the status of the following IE Bulletins:
a.
'(Closed)-IE Bulletin 80-07, BWR Jet. Pump' Hold-Down-Beams. The.1icen-see's response to this bulletin committed to' reduce the.preload on'the; jet pump hold-down beam from 30 -kips to 25~ kips and to perform periodic ;
inspections as a part of the inservice inspection plan.(Ref. Page 3-25-
~
of NUREG u831).
'
The inspector reviewed the 'nstallation data forEthe jet l pumps,5 kich
-
i verified the preload reduction, Land discussed theilicensee'.s plans'for-
. inservice-inspection with the ISI coordinator.
_
<
f(Close'd) IE Bulletin 80-21,' Valve Yokss Manufactured by Malcolm Foundry}
n.
Company, Inc. The. licensee's respon.se No.' AECM-81/208 ' dated ' June -16, 1981 ~' states - that ; there.- are-no : safety _related Walves1with Malcolm
,
Foundry Company parts ;in use ore planned L.for~ use. ct the Grandj Gulf..
,
' Station.
~ '
'
. C.
Safety.Related' Structures (Unit 1);
,
- The inspector conducted. visual inspections ofusafety related structures andl i
. reviewed the Quality Assurance documentation foritheir fabrication ~ installa-:-
?tions. The safety related structures" inspected were-as follows:
E'
'
-
.
m.
'7 w
i
--
O
'
r
,
<;.-
h.-
.
,,
,
,
..,. j <
,,
,
,,,
~,-
-
-
-
.
.i o.
4 a.
Support Steel for RHR
"A" Heat Exchanger Documentation reviewed included Work Plan and inspection Record ( P /IR) No. QIT10-V-00245B0A;
,
WP/IR No. QT22-W-07137 and supporting records.
,
b.
Support Steel for RHR
"B" Heat Exchanger - Documentation reviewed included WP/IR QIT10-V-0024580A and supporting records.
,
c.
Pipe Hanger No. QIE12G021C03 - Inspected for conformance to the requirements of hanger drawing no. QIE12G021C03 Rev. 3, "Feedwater and t
Return from Reactor Water Cleanup System" and system piping isometric No. HL-1328K Rev. 9 documentation included "Large Pipe Hanger Installa-
>
tion Card", "Large Pipe Hanger Inspection Record", and " Supplemental i
l Checklist for Concrete Expansion Anchors".
d.
Pipe Hanger No. QIE51G004A02 - Inspected for conformance to hanger
drawing QIE51G004A02 Rev. 8, AWD Piping 1sometric HL-1347A " System
Piping Isometric Main Steam to RCIC Pump Turbine and RHR".
Documen-tation included "Large Pipe Hanger Installation Card", "Large Pipe Hanger Inspection Record", and " Supplemental Checklist. for Concrete Expansion Anchors".
There were no violations or deviations in this area of the inspection.
9.
Containment (Steel Structures and Supports) - Review of Quality Records-The inspector reviewed-the quality records for the erection of the contain-ment liner plate. The containment liner was fabricated and erected by CB&I in accordance with ASME B&PV Code Section III 1971 edition through Summer 1973 addenda.
The records reviewed included the CB&T record drawings for shell rings No.
11-through 15, and the record-drawings for the " Cutouts in the Dome Hip Course for Repair".
The repair involved replacement of segments of'the; containment plates which were damaged by the collapse of a construction crane during..a wind storm.
There were no violations or deviations noted 'during this phase of the.
inspection.
-10.
Reactor Vessel Internals The reactor vessel internals ~ were. installed in _accordance with the ASME B&PV Code Section III 1974 edition' summer 1976 addenda.
- The inspector reviewed -the documentation for the installation. of >the' jet -
-pump ' inlet c mixers. ' Thi s' documentation D included : Travelers ' Nos. JPIM-AT, JPIM-BT, JPIM-CT, JPIM-DT, JPIM-ET, JPIM-FT, JPIM-GT, -'JPIM-HT, -JPIM-JT, _
.
JPIM-KT, JPIM-MT, ' and JPIM-NT ' for.the original - jet. pump. installation;
Receiving Inspection L Re' ports; _ Jet; Pumpi. Tensioning,o Vibration : Program -'
~ Traveler JPT-T1; and ~Jointf Process Control: Sheet, JHPT-J1.
'
_
'
,
-
t
E
--
,
..... -
.
There were no violations or deviations in this area of the inspection.
11.
Safety Related Components The inspector selected several safety related pumps and valves for a review of QA records concerning vendor certification; receipt inspection and storage; and installation and protection documentation. Components selected for documentation review were as follows:
a.
Recirculation Pump A - Byron and Jackson Pump Ser. No. 741-S-1276 b.
Recirculation Pump B - Byron and Jackson Pump Ser. No. 741-S-1277 c.
RHR Pump A - Pump No. QIE12C002A-A d.
RHR Pump B - Pump No. QIE12C0028-B e.
14-Inch Gate Valve - Valve No. OIE12F0398 f.
14-Inch Gate Valve - Valve No. QIE22F0368 g.
12-Inch Gate Valve - Valve No. QIE12F042 h.
24-Inch Gate Valve - Valve No. QIB33F0238 1.
12-Inch Gate Valve - Valve No. (IE22F004 j.
24-Inch Gate Valve - Valve No. QIB33F023A There were no violations or deviations noted in this area of the inspection.
,
- _
. -.
,