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NUCLEAR REGULATORY COMMisslON
),. I WASHING TON. D. C. 20555
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March 7,1978 MEMORANDUM FOR:
D. B. Vassallo A/D for Light Water Reactors Division of Project Management NRR FROM:
J.-H. Sniezek, A/D for Field Coordination Division of Reacto-Operations Inspection IE
SUBJECT:
ARKANSAS POWER AND LIGHT COMPANY, ANO UNIT NO. 2 (DN 50-368) - FACILITY COMPLETION STATUS Region IV has provided us with update information regarding the status of completion of construction and preoperational testing at the subject facility.
Enclosure A contains a listing of outstanding items remaining to be resolved.
No significance' categories have been established at this time. After further evaluation of each outstanding item, signifi-cance categories will be identified to define the operational mode (fuel loading, criticality, etc.) for which specified items are required to be resolved.
Enclosures B and C contain_the status of preoperational i
testing and facility construction respectively. Unless otherwise specified in the enclosures, the information is current as of March 1, i
1978.
l Due to the incomplete status of this facility regarding preoperational testing and operational preparedness, a number of inspection requirements remain to be completed. Therefore, the outstanding items provided in Enclosure A are expected to be only a partial listing of the items requiring resolution prior to issuance of an operating license.
Pending satisfactory resolution of the items listed and others that may be identified as a result of completing the inspection program, IE will make a finding that the facility has been completed in substantial agreement with docketed counitments and regulatory requirements.
The licensee's projected fuel load date is April 24, 1978. The Region believes that June 1,1978, is a more realistic date.
8504120267 840606 M
. Sniezek, D for Field KILLEFE84-367 PDR Coordination ivision-of Reactor Operations Inspection IE
Enclosures:
A.
Outstanding Items B.- Preoperational Test Status C.
Status of Construction and
. Construction Deficiencies cc: See next page CONTACT:
K. W. Whitt.
' (492-8019) 1
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D. B. Vassallo March 7,1978 cc:
H. D. Thornburg, IE N. C. Moseley, IE L. B. Higginbotham, IE N. M. Haller, IE K. V. Seyfrit, IE E. M. Howard, RIV G. L. Madsen, RIV J. E. Gagliardo, RIV R. S. Boyd, NRR J. F. Stolz, NRR R. E. Martin, NRR e
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e ENCLOSURE A OUTSTANDING ITEMS This enclosure summarizes the outstanding enforcement, unresolved and open items for which Region IV will require resolution or completion prior to endorsing a finding of readiness for operation of ANO-2. The expected completion date (if known) and the significance of selected items is also provided.
A.
Resolution of the Following Enforcement Items (Noncompliance and Deviations) 1.
Welding procedure specification with greater amperage range than qualified. This item could result in the requirement to reweld the main steam and feedwater piping welds which were made under the non-qualified procedure. A meeting between NRR-DSS and the licensee was recommended by RIV.
(77-04) 2.
New fuel receipt inspection procedure did not contain the features required by QA Manual..(77-21)
I 3.
New fuel receipt inspections ' performed by personnel who were not qualified or certified in accordance with QA Manual require-ments.
(77-21) 4.
Steam generator hydro procedure changed without the required j
approvals.
(77-21) 3 f
5.
FSAR drawings which are outdated.
(77-26)
I 6.
Preservice examination records of the reactor pressure vessel are missing or do not correlate to the procedure. This item.
could result in a rerun of the reactor vessel preservice examin-ation.
(77-27) 7.
Test records for test procedure 2.048.02 not documented in accordance with Startup Administrative Procedures.
(77-29) 4 8.
Replacement of modules in an electrical penetration assembly)
(EPA) were perfonned without'a Startup Work Request.
(78-03 9.
Leaking EPA was not documented by an NCR.
(78-03) 10.
Steps in two completed test procedures were not verified as being completed with an initial and date.
(78-03) 11.
A test deficiency in a completed test procedure was not closed out when the test was given final approval.
(78-03)
. e.,e n 99
l
- i 12.
Operating, emergency and maintenance procedures not completed prior to applicant's comitted date.
(77-11, 77-16 and 77-24) 13.
Test procedures not issued 90 days prior to scheduled fuel loading date. This item has had significant impact on the completion'of the inspection procedures in MC 2514.
(77-26)
B.
Resolution of the Following Unresolved Items (URI)_
1.
URI 7711-3: No apparent means of controlling changes to safety related electrical drawings. This item has been referred to the Vendor Inspection Branch for resolution.
2.
URI 7711-4:
PM Program for Unit 2.
The applicant is working on the preventative maintenance program for safety related i
i equipment.
IE/RIV will review the program and the basis for selected PM items during a future inspection.
'I j
Control Procedures for fire protection /
l prevention. NRR has requested that the applicant provide controls consistant with the guidance of BTP 9.5-1.
Region IV strongly supports this effort.
l 4.
URI 7711-6: Master surveillance test schedule. Applicant indi-cates that the completion of this item is awaiting final resolu-tion of TS issues.
' 5. -
URI 7711-7: Use of CASE or ASME for vendor qualifications. This item has been referred to IE management for resolution.
6.
URI 7711-8: Procedures to control the shipping, handling, and packaging of safety related equipment.
7.
URI 7712-1:
Inadequate receiving inspection documents for two instrument devices.
i 8.
URI 7719-1: QC hold points in preoperational test procedures.
This item has been referred to IE headquarters for guidance.
9.
URI 7720-2: Ventilation power supplies for electrical equipment rooms. The significance of this item is due to the fact that i
Rm 2091 houses inverters 2Y22 and 2Y24 which are associated with m.
Wr L
. the green and blue buses. This room is cooled, however, by chillers _ powered from the red bus. The applicant has proposed a fix to thi' problem which will be completed prior to 0L a
issuance.
10.
URI 7720-3:
Cable separation discrepancy in Room 2091.
11.
URI 7721-2: Sureve111ance of spent fuel pool wall. This item
.has been submitted to NRR via IE headquarters to recommend inclusion in the TS.
12.
URI'7722-1:
Installation of piping restraints. This item
-involves problems identified with grouted anchor bolts.
13.
URI 7722-2: Qualification tests of cable penetration seals.
This item could have significant impact if the applicant's penetration seals do not meet the criteria of staff position PF.6. An expected ccmpletion time for this issue is unknown.
14.
URI 7724-2:
Modification of local handswitch (at MCC) for motor operated valves in the shutdown cooling system. The applicant-has issued a Design Change Package to correct this problem.
15.
URI 7729-1: The test loading of 480V buses 2B5 and 286 did not meet design.
l 16.
URI.7729-3: The initial fuel loading draft procedure does not i
contain all of the features required by Reg Guide 1.68.
17.
URI 7801-1: Core protection calculator system procedures will be revised to provide failure response testing of the CPC.
C.
Open Items Region IV has identified fifty-(50) open items which are still outstanding and must be resolved or closed prior to our finding of readiness for OL. The following is a list of the more significant open items.-
1.
Verification of the installation of fire stops, seals, and-cable tray covers.
2.
Verification of the' installation of conduit for cable EC3-138 to the HPSI pump.
3.
' Verification of the installation of thennal sleeves on cable R2SSIE1E in' cable tray EC-173.
.=
. 4.
Final verification that cable tray and conduit seismic supports are installed as specified.
5.
Verification of cable tray and conduit loading.
6.
Review and verification of completed preservice inspection records.
7.
Verification of completed pipe support / restraint systems.
8.
Completion of preventative maintenance requirements for equipment under startup's control.
9.
Testing of relief valves in accordance wtih ASME XI. Proposed ISI program includes only pressurizer safety valves and steam generator safeties / reliefs.
10.
Revise job order fann and provide space for indicating (or docu-menting) the post-maintenance testing required.
j 11.
Issue QC procedure for control of design changes.
12.
Issue test control procedure (See URI 7711-6) which itemizes i
TS surveillance requirements and responsibilities for their performance.
3 13.
Resolve cable tennination problems relating to DCP-20.
14.
Review of inspection procedures and inspection results for the l
visual examination of core internals following hot functional testing.
l 15.
Review and verification of the training and certification of l
refueling machine and polar crane cperators.
16.
Verification that plant protection system (PPS) bistable set-points are reset prior to fuel loading and that section 7.4.3 of the PPS preop test is rerun.
l-i 17.
Verify applicant's review of the HPSI injection valves being 60% vice 80% open for injection.
L l
18.
Verification that functional checks deleted in test procedure l
2.048.02 are perfonned in another test.
19.
Verify that HPSI test procedure is revised to test capability of
- two.HPSI pumps to operate on connon suction line.
4
20.
Verify that equipment history program includes vendor reappraisal.
21.
Verify that CPC equipment history M maintained.
22.
Verification of the program to purge all EPA's and establish a surveillance program for monitoring their N2 pressure.
23.
Review and verification of the completion of significant items on the startup~ organization's punchlist.
9 l
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ENCLOSURE 8 PREOPERATIONAL TESTING STATUS The applicant has identified 186 test procedures which are classed as preoperational tests.
In addition, the applicant has identified 28 startup tests which must be completed prior to fuel loading (0L issuance).
The applicant's post fuel load startup testing program contains 66 test
)
procedures.
The table below summarizes the status of the applicant's test program:
Preop Pre Core Post Core
_ Tests SU Tests SU Tests Number of test procedures 186 28 66 Procedures approved / issued 180 24 17 Tests completed 119 6
0 Test results reviewed 91 2
0 Test results-final approval 35 1
0 Status updated as of February 10, 1978.
l 4
e
ENCLOSURE C STATUS OF CONSTRUCTION AND CONSTRUCTION DEFICIENCIES Construction Status As of February 24, 1978, the following safety related systems had not been turned over from construction to startup:
1.
The applicant has identified 428 pipe supports / restraints that had to be installed with 34 needed prior to fuel loading and 122 needed prior to initial criticality.
2.
The detector tubes for the radiation monitors in the ventilation system had not yet been installed. Applicant representatives stated that final installation would be delayed until immediately prior to fuel loading to prevent inadvertent breakage by construction activities.
3.
The reactor building polar crane has been load tested but has not been turned over for testing because construction continues to need it in support of their activities.
4.
The cable spreading room sprinkler system is yet to be turned over.
i 5.
The security fence, intrusion alarm, and security lighting systems are not yet complete.
1 It is noted that numerous construction items remain to be completed for systems that have been turned over to the startup organization. These items have been identified on applicable release exception lists and have been added to the startup punchlist. The punchlist will be reviewed in detail during a future inspection. Significant open items will be added to the open items list (Enclosure A) at that time.
Status of CDR's As of February 24, 1978, thefollowingCDR's(10CFR50.55(e) reportable deficiencies) have not been resolved:
1.
HPSI system low flow rate - vendor group is evaluating the CE small break analysis and its inputs.
2.
Emergency chillers for control room - the design change to correct the wiring errors is not yet complete.
3.
Motor operate.d valves circuit design - the applicant has not yet submitted a final report (overdue) 4.
Brittle fracture potential in main feedwater piping - the applicant plans to replace the affected piping. The final report is overdue.
9
. 5.
Cracks in LPSI pump support columns - the applicant has not yet submitted a final report in this issue which is now overdue.
6.
Ground indication in Raychem cables - the applicant has not yet submitted a written report on this issue which is now overdue.
l
- 7.
Grounds in diesel generator field flashing circuit - the written report, which is now overdue, has not yet been submitted.
8.
Fused contracts in emergency feedwater control relay - written report is due on February 27, 1978.
9.
LPSI pump impellar retainers'- the written report on this item is due on March 19, 1978.
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