ML20049A750
| ML20049A750 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/28/1981 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Sniezek J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8110020212 | |
| Download: ML20049A750 (9) | |
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September 28, 1981 MEMORANDUM FOR:
J. H. Sniezek, Director, Division of Resident and Regional Reactor Inspection IE FROM:
R. H. Engelken Director, Region V
SUBJECT:
SOUTHERN CALIFORNIA EDISON In accordance with Inspection Procedure No. 943008, the attached enclosures list the remaining open items that require resolution before a finding of readiness for operation may be endorsed by Region V.
The significance of each identified item, relative to the planned issuance of the operating license, is discussed.
Original signed by R. H. Engelken m[
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Enclosures:
4 00T1 1981*
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Appendix A - Outstanding Items Including Enforcement v.s. manz anamon
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and Unresc1ved Items 4
Appendix B - Preoperational Testing Status Appendix C - Construction Status 4
Appendix D - Status of Inspections Required by MC 2512, w
MC2513.MC2514,MC2593,MC2594(Summary) cc:
H. D. Thornburg, Director DS&RSI B. K. Grimes Director, DEP D. Thompson, Director, E&I N. C. Moseley, Director, DPDAA L. J. Cobb, Director T&A I
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Appendix A Outstanding Ityas Including Enforcement and Unresolved Items I.
Opera tions A.
Enforcement Items 1.
Inadvertent operation of LPSI pumps with shut suction valves (requires verification of licensee corrective action).
B.
Unresolved Items None C.
Follow-up Items 1.
Applicant to complete Operating Instruction Index and IE to insure confonnance with Regulatory Guide 1.33.
L Review applicant's corrective actions for RCS instruments that did not meet vendor's specified tolerances.
3.
Review corrected Instrument Error Analysis for CILRT to be submitted by applicant (does not affect acceptability of CILRT).*
4.
Verify upgrading of calibration requirements for permanent plant instrumentation used during testing.
II.
Construction 4
A.
Enforcement Items c
1.
Inadequate cable' separation in cabinets.
B.
Unresolved Items 1.
Class 1EinstrumenttubingconnectEdtonon-class 1E tubing.
4 C.
Follow-up Items 1.
IE Bulletins a)
IEB-79-14:
Seismic analysis of as-built safety-related piping system.
b)
IEB 80-05:
Vacuum cono tions resulting in damage 1
to holdup tanks.
- Does not need to be completed prior to fuel loading.
L.
Appendix A.
c)
IEB-79-15: Material deficiencies in Inger-Rand pumps used for hi/lo pressure core spray and RHR pump.
d)
IEB-80-05:
ESF. reset controls 2.
50.55(e) Items-Excess bypass or"recirc flow 'for HPSI pumps which
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a.
reduces the net discharge flow of the; pumps below specified requirements.-
b.
HFA relays. manufactured by. GE'and supplie'd by ITE have cracked coil spool i.nsulators which might result in fa'ilure of. relay;to operate ' properly.
' Prema$ure time-out condition exhibited by certain c.
Agastat Model 7000 Series time delay relays.
d.
Use of incorrect material in-keys between motor drive shaft and pinion gear on Model SMB-4 Limitorque valve operators.
e.
Loss of DG set output due _to unit tripping on high crankcase pressure signal during preop. testing.
f.
Improper assembly of coaxial connectors in elec.
containment penetrations.
g.
Steam generator feedring deformation.
h.
Pressurizer safety valve operability instabilities during test.
i.
Cracks on hard facing of guide lug inserts for RV internals, J.
Flammable spray adhesive on fireproof insulation for elec. cable.
k.
Diesel' generator engine camshaft bracket failure.
1.
Incorrect welding procedure used on reactor vessel head vent.
m.
Equipment did not remain in emergency mode upon reset after ESF actuation signal.
III. Security Outstanding Enforcement, Unresolved, or Follow-up Items None r
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r Appendix A 0 IV.
Radiation protection Outstanding Follow-up Items 1.
Confirm appropriate calibration.of process and effluent radiation monitoring systems.
2.
Representativeness of particulate and iodine sampling of the gaseous effluent stream needs justification.
3.
One entrance to a potential high radiation area adjacent to the fuel transfer tube was not controlled.
4.
Confirm that the 9.5 millicurie calibration source is NBS traceable and appropriate documentation exists.
5.
. Confirm procedures require periodic sampling of nonradioactive systems which is final action to complete response to IEB 80-10.
6.
Confirm corrective action identified as the result of IEC 80-14.
7.
Confirm any correct-ive action taken as the result of IEC 81-07.
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l Appendix B PRE 0PERATIONAL TESTING STATUS Percent Complete Test Procedures
' Tests Results-Completion Test Type No.
Approved by TWG Completed.
Approved by TNG Due Preoperational/
Acceptance Tests 92 100%
86%
30%
OL Issuance Before Low Post Core Loading Power Physics Hot Functional Tests Tests 8
40%
0%
'0%
Before Power Low Power Ascension Physics Tests 7
57%
0%
0%
Tests Power Ascension Before Tests 17 20%
0%
0%
Full Power q
y M 4 0
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t Appendix C Construction Status Construction is greater than 99% complete.
Systems / structures requiring significant repair effort to complete include:
Steam generator feed ring repair (est. compl.11/3/81)*
Pressurizer relief valve piping (est. comp. 10/15/81) 1 i
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l Not needed for fuel loading.
Appendix D Inspection Program Status I.
Construction Inspection Program (MC 2512)
The bulk of the effort remaining in this area involves review of records and as-built drawings. A small amount of " observation of work" remains to be completed for electric components and systems, and inspection of the permanent fire loop installation and " procurement, receiving, and storage" remains to be completed.
II.
Preoperational Inspection Program (MC 2513 & 2593)
A.
Oparations l
Areas requiring significant inspection effort include the I
following:
I Verification that Plant, Operating, and Maintenance procedu;es i
have received the required reviews and approval.
Review of the draft facility Technical Specifications.
Witnessing of Tests of E gineered Safety Features, and Reactor Protection System and Evaluation of the Results of these j
tests.
I Verification that test results are evaluated by the licensee, and comparison of as-built plant to the FSAR description.
1 B.
Construction l
N/A C.
Security l
The applicant does not presently have an approved physical security plan for Unit 2, and should.have one prior to a j
security pre-operational inspection and licensing.
The applicant I
is presently negotiating with the NRC staff _to achieve an approved security plan. None of the preoperational security and safeguards inspection has yet been conducted.
- However, based on discussions with the applicant's security ~ representatives, a mutually acceptable time for this team inspcetion'(October 13-23, 1981) was selected.
)
l D.
Radiation Protection 1.
Environmental Protection (Final Preop. Inspection)
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- . Appendix D.
2.
Emergency Fianning (covered by special IE Appraisal Program) 3.
Completion of Initicl/ Retraining of Health Physics Staff for Unit 2.
Also radiation safety / emergency planning training of other Unit 2 personnel (except NRC licensed individuals).
4.
Review of Health Physics (radiological protection) procedures.
5.
Review Health Physics portable instrumentation'and equipment, and laborstory instrumentation and related calibrations.
6.
Review respiratcry protection procedures to be completed, approved, and implemented after July 24,-1981.
7.
Verify the preoperational testing of the ' Coolant Radwaste, Coolant and Boric Acid Recycle and Miscellaneous Liquid Radwaste Systems and examine the test results.
8.
Verify the preoperational testing of the Gaseous Radwaste System and examine.for test results.
9.
Inspect the HEPA and charcoal filter systems and examine the results of inplace testing of these systems.
10 Verify initial calibration of liquid effluent tank volumes and flow measuring devices.
- 11. Verify installation of containment purge and vent stack wide range, main steam lines, and normal semple lab isolation monitors.
12.
Evaluate the licensee's Units 2/3 capability for measuring radioactivity in various types of samplas.
Examine the quality control program for analytical measurements.
III.
Startup Program (MC 2514)
A.
Operations The principal outstanding inspection requirement in this area is the completion of the TMI-related inspection defined in to Temporary Instruction.TI-2514/01. The present status is that inspection of these areas is just commencing.
Another area which is incomplete is that of review of startup test procedures.
The remaining effort required in this area, however, is limited to verifying that the procedures have received proper final review and approval, u
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' Appendix D.
B.
Construction, Security and Radiation Protection N/A E