ML19220B407
| ML19220B407 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/10/1971 |
| From: | Howard E, Hunnicutt D US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19220B403 | List: |
| References | |
| 50-320-71-01, 50-320-71-1, NUDOCS 7904250697 | |
| Download: ML19220B407 (6) | |
Text
I U. S. ATCMIC ESERGY COFMISSIO:;
REGION 1 DIVISICS OF COMPLIANCE Report of Inspection CO Report No. 320/71-1 Licensee:
Metropolitan Edison C;:pany (Met Ed)
Three Mile Island Unit ;;o. 2 License No.
CPPR-66 Date of Inspection:
January 18 - 19, 1971 Date of Previous Inspection:
October 8 - 9, 1970 Inspected by:
M
~8
.Z//C/7I w
D. M. Hunnicutt, Reactor Inspector (Principal)
'Date Reviewed by:
9/7.
wh
,_2-/O -7 /
I. M. Howard, Senior Reactor Inspector Date Proprietary Information:
None i
SCOPE A routine, announced inspection was =ade of Unit No. 2, one of the two 2535 r,it pressurized water reactors (B&W) under construction on Three Mile Island, near Middletown, Pennsylvania. The inspection effort was directed toward an appraisal of the performance of the licensee-contractor effort of various items listed in PI 3800/2 and included an inspection of Attachment E -
Other Class I Structures, " Steam Generator Support" (4800 and 5400) and one outstanding ites, previously reported.
SUMMARY
Safety Items - None Nonconfer=ance Items - None Unusual Occurrences - None Orbar Sienificant Items
/, fire occurred on January 19, 1971, in some temporary structures assigned to Unit No. 1.
No personnel were injured nor were Unit No. 2 buildings or equipment involved in the fire. The inspector terminated the inspection due to the confusion resulting from the fire.
v gs7[~
r I
gb b 4 a) 7904eso 977
. 2 Manarement Interview The inspector informed Mr. Hreczuch that the inspection of the steam generator support indicated that the procedures, instructions, and specifications are in agreement with conmitments in the PSAR.
DETAI LS
~
A.
persons Contacted Met Ed Mr. Gene Hreczuch, Construction Engineer Mr. Earl Allen, Resident QA Supervisor UE&C Mr. J. E. Fant, Site'QC M_anager Mr. Paul Da '
- f, QC Engineer B.
Construction Status Mr. Ereczuch estimated that Unit No. 2 was approxi=ately 127. co=plete, based on man hours expended.
C.
- Procurement documents (B&R specification 2555-64) have been rvvised to specify hydrostatte testing of pipe and camponents by the vendor and now specify the qualification requirements for NDT personnel.
D.
Steam Generator Support (SCS) i The inspector performed a review of the QC system for the SGS in accordance with Attachment E - Other Class I Structures, " Structures and Supports", PI l
3800/2. The inspection covered items 5405.03, 5405.04.b.1 through and in-cluding f.5; 5405.05.a.1, a.2, and a.3; and 5405.06.a.2 and a.3.
The pro-
+
cedures, ins t ru ct ions, and specifications are in agreement with the ce=mit-t
=ents in the PSAR. No deficiencies or omissions in procedures or record keeping related to materials, testing, handling, installation, or i=plementa-tion of QC inspections were observed during the inspection.
- C0 Report No. 320/70-6 N_.
i 326 t
f At t achment E - Other Class I Structures (Steam Generator Suonort)
The following items were again audited and the results found to be in agree-ment with previously rep..ed results which are documented below showing dates of initial audit.
Insrection Items 4500
'JE LDISC CO Report No.
OK 69-5 du L805.03 Implementation of OA Procram 4E05.04 Review of CC Systet a.1 Qualifications'of weld procedure.
11/5/69 dw a.2 Qualifications of welders 11/5/69 dw 3.3 Qualifications of NDT techniques 5/28/70 dh a.4 Qualifications of NDT technicinas 5/28/70 dh
%.1 Identification of weld location 5/28/70 dh b.2 Identification of welder 5/28/70 dh b.3 Identification of weld procedures 11/5/69 dw b.4 Identification of NDT technician 3/30/70 dw b.5 Identification of NDT procedures 5/28/70 dh i
b.6 Identification of KDT results 11/5/69
. lw e.1 Radiograph quality 5/28/70 dh e.2 Evaluation of weld quality 11/5/69 dw e.3 Magnetic particle examination 10/9/70 rib e.4 Dye penetrant exa=ination 11/5/69 dw e.5 Ultrasonic examination 5/28/70 dh e 6 Correlation of records to welds 11/5/69 dw f.2 Defect re= oval verification 11/5/69 dw f.6 Acceptance of repair 11/5/69 dw g.1 Material Receipt verifications 5/28/70 dh g.2 Pre-issue storage conditions 11/5/69 dw STRUCTURES AND SUPPORTS (5400' 1.
Implementation of OA Program (5405.03)
UE&C is the construction contractor and is responsible for the concrete construction at the plant. QC surveillance of the manufacture and place-ment of concrete is perforced by an independent testing organization, PTL.
A PTL inspector observes the preparation of cadweld splices and cust ap-prove the finished splice.
telected cadwelt. splices are re=oved (random sa=pling method) and pulled to destruction in the testing lab that has been crected on the site.
The test results are reported to UE&C's QA k--
organization.
Size, spacing, and' tying of the rebar is checked by UE&C's QA organization against the coplicable drawing. Rebar test r ports, m
I j
r r).
. ), 3 r/
it
- t. 4-
-L mill tests, and receiuing inspection reports are under the record con-trol of UE6C.
This file is available for inspection by the applicant and the Met Ed QA organization.
PTL inspectors at the pour site have an inspection check sheet that must be completed prior to approving placement of concrete.
This inspection includes that the designated load arrives at the proper location, size and splicing of the rebar. The PTL inspector performs slump tests, checks for air entrainment, the batch temperature, the truck revolution counter and prepares the test cylinders as required by the procedure (QC-2-1).
A record is maintained of the disposition of each load of concrete.
B&R perfor=s QA audits of the concrete manufacturer (UELC), concrete place-ment, and PTL's QC surveillance of the work in progress. Additional QA audits are made of the efforts of UE&C, PTL and ESR by Met Ed and HPR ssociates for the ovner.
A weekly QA meeting is held at the construction site to review performance in all areas, including concrece. A monthly meeting is held at the home office of UE&C to review overall progress. Minutes are kept to document the action taken or required on specific problems.
The inspector reviewed the records and held discussions with personnel at the construction site, which indicated that these QA/QC organizations are functioning as described. These organizaticns meet the require-cents for QA/QC stated in the PSAR and generally meat the intent of the proposed QA criteria in Appendix B, 10 CFR 50.
Unit No. 2 received its CPPK prior to the requirements of Appendix B becoming a require-ment of the CPPR.
2.
Review of OC System (5405.04) a.
Materials Chemical Coenosition (5405. 04.b.1)
The chemical certifications were cudited. No deficiencies were noted.
b.
Materials Physical Characteristics (5405. 04.b. 2 )
Concrete ingrediecte nave been previously checked and reported in CO Report No. 289, 320/70-5.
c.
Materials NDT (5405.04.b.3) 2 The rebar was shipped with the heat nu=her and identification numbers sta= ped on them.
The mill certifications were checked to assure that the numbers and materials were correct. UT or other NDT methods (m-are not required on pedestals during or subsequent to construction co=pletion.
4 r22[}
eaaa u
d.
Bandline of Nonconforming Material (5405. 04. c. 5 )
Nonconforming materials are either rejected or placed i until proper disposition has been completed.
n quarantine and handling is contrriled by UE6C procedure QC-2-17 Receiving inspection Nonconfor=ing Materials. "
" Control of c.
Storace Identification and Centrol (50 05. 04. d. 2 )
Receiving inspection is assigned to the field supervis designees. The storage effort or QC or his
" Storage Co" col."
is governed by UE&C procedure QC-2-3, f.
_ Installation Specs on Soecial Cococaents (5405. 04. f. 3)
ELE, the AE, prepared the specifications for UESC followed the specifications in addition the reactor vessel support.
tions for Class I concrete (QC-2-1).
to the UE&C specifica-tion of rebar were checked by UE&C, BLRDrawings of as-built installa-concrete to assure adequate rebar and that, and Met Ed prior to pouring rebar was properly placed.
g.
NDT Testine and Insoection (5405. 04. f. 5 )
NDT testing is not included required testing stated in UE&C procedure QC 21 Inspection by Met Ed and B&R in addition to required UESC surveilla and audits PTL perforced inspections as stated in nce of PTL.
5405.03.
3.
Follewuo Record Review (5405.05) a.
Paterials Records (5405.05.a.1)
All records requested by the inspector were readily prod personnel.
The records included materials certifications uced by UELC analyses of concrete ingredients, chemical and physical check
, chemical inspection during erection of the reactor vessel sup l
s on assure iencies were noted in_any of these records No defic-b.
Receipt Records (5405.05.a.2,[
The proceduros defined the responsibilities of the per o records verified that the procedures had been followeds nnel. Site l-
- storage, had been identified. quarantine and released for use, were properly marked and Materials in
~
=
the suppliers certifications and rechecks by PTL wereCertificatio
=um allowable IL=it and were within the stated specifications f above the mini-k_
use.
No deficiencier were noted in any of these or records.
{'
i, kn i
,. 2 I
I
.- c.
Installation Records (5405.05.a.3)
Installation records for the reactor vessel support indicated that the rebar had been checked as to size, location, and met the require-ents.
The drawings indicated that, dimensionally, the pedestal had been constructed as required.
Inspection and surveillance records in-dicated that the support was constructed as required.
The concrete met the place =ent conditions and the 28 day cylinder breaks were above 5000 psi (mini =um average recorded for two cylinder breaks was 5430 psi).
The concrete net the requirements specified by the design mix, temperature, sluep and air entrainment prior to pouring.
4 Followuo Observations of Work (5405.06)
Installation (5405.06.a.2) a.
UE&C records were reviewed covering the site receipt inspection and acceptance cf the reactor' vessel support. The records contained infor=ation on material and dimensional checks, co=pletion of physi-cal examinations and other data to support a conclustion of accepta-bility with respect to the procurement, storage, handling and in-sta11ation of the reactor vessel support.
(
b.
Ieolementation of QC Insoections (5405.06.a.3)
Copies of the vendor inspection reports made by Met Ed are kept at the construction site. Approximately 14 vendor inspections have been cade since December, 1970. These audits cet the intent for a systematic program, and planned and periodic audits as stated in Criterion IVIII, 10 CFR 50.
There is no firm plan to cover the type and f requency of the audit activities. However, the number and type of audits appear to assure control. Unit No. 2 is co=mitted to at-tempt to adhere to Appendix B,10 CFR 50, as far as practical. The records audited substantiate that the applicant is making a reasonable effort to meer this co=mitment.
w 330 m
_