IR 05000320/1977028
| ML19220B673 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/03/1977 |
| From: | Caphton D, Rebelowski T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220B670 | List: |
| References | |
| 50-320-77-28, NUDOCS 7904270197 | |
| Download: ML19220B673 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
77 7P Docket No.
50-320 License No.
CPPR-66 Priority
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Category B1 Licensee:
"etropolitan Edison Comcanv P. O. Box 542 Readinc. Pennsvlvania Facility Name:
Three Mile Island, Unit 3 Inspection at:
Middletown, Pennsylvania Inspection conducted:
June 28-30 and July 1, 1977
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/- 3 - 77 Inspectors:
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s date signea T. A. Rebelowski, Reactor Inspector date signed date signed Idr b
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a Approved by:
. O' [h 3 /77 D. L. Caphton, Chief, Nuclear Support
.date signed
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Section No. 1, RO&NS, Branch
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Insoection Sumary:
Insoection on June 28-30 and July 1,1977 (Recort Mo. 50-320/77-28)
Routine, unannounced inspection of preoperational implementa-Areas Insoected:
tion program in the area of design changes; preoperational test results evaluation; hot functional test program review; loss of electric power test problems; draw-down test; observations of physical plant; previously identified unresolved items; and building spray pump motor bearing failcre. The inspection involved 38 inspecto-hours onsite by one NRC inspector.
Of the eight areas inspected, no items of noncompliance were identified.
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Results:
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790427oin
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l 81 126
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Region I Fom 12
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(Rev. April 77)
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rcTAILS_
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Persons Contacted _
Metrocolitan Edison Comoany
- Mr. B. Bezilla, PORC Administrator
- Mr. J. Hilbish, Station Nuclear Engineer General Public Utilities Service Corocration (GPUSC)
Mr. R. Fenti, QA Aeditor Mr. C. Gatto, Engineer Mr. I. Porta, Engineer
- Mr. M. Nelson, Technical Engineer Mr. J. Roberts, Engineer
- Mr. R. Toole, Test Superintendent
- denotes those present at the exit interview.
Licensee Action on Previous Inscection Findinas
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2.
320/76-17-01: A review of the test re-d sults of the flush procedure MTX 110.4, Nuclear Service CloseFin (Closed) Unresolved Item Cooling Water System was conducted. achievement of f
system that have been flushed.available have been noted o ditional turnover package and in the test plan.
The licensee has completed 320/77-19-01:
R 1A (5-27-(Closed) Unresolved Item the testing of the pressurizer coded relief valves RC -The test This 77) and RC-R-1B (6-2-77).tive lifts within the acceptable crit item is resolved.
The licensee has addressed 320/77-14-03:
6, the problem of block walls in a 10 CFR 50.5S(
(Closed) Unresolved Item The completed upon receipt of licensce's accepta
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1977.
This item is resolved.
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(0 pen) Unresclved Item 320/77-17-02: The licensee has issued the following procedures:
TP 600/3, 600/10, 600/13, 600/21, 600/30, and 330/5. Two tests remain to be issued TP 600/4 and 600/20.
This item remains unresolved.
(Closed) Unresolved Item 320/77-23-01:
The code insoector has documented his observance of the test results associated with TP 200/4 (MTX 147.5) Reactor Coolant System Hydrostatic Test, Section 10.9, Page 38 as satisfactory.
This item is resolved.
3.
Precoerational Imolementation Procram a.
Desien Chances The inspector reviewed three recently completed design change packages. The packages included:
(1)
Field Change Request 2355 which addressed repairs to motor control center 2-11EB (completed January 28,1977);
(2)
Field Change Request 175 (includes FC89) which addressed (
the replacement of letdown orifice in the makeup system (completed March 9, 1977); and, (3)
Field Change Request 178 (includes FC118) which addressed
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the addition of current transformers to RC pumo motor electric monitor.ing systems.
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The inspector verified that each design change was reviewed by the licensee for:
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Engineering evaluation;
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Required retests;
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Effect on previous tested systems;
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Required procedures changed to reflect changes;
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Updating of diagrams where required; and,
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Review cf test results by cognizant engineering per-
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sonnel.
No inadequacies were identified.
This item is resolved.
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b.
Temocrary Jumoer/Byoass Loa A review of the irplementation of the Administrative Procedure 1013, Bypass of Safety Function and dumper Controls, dated June 6,1977, Revision 5, indicated that logging of jumpers was performed. Two areas of concern were identified:
(1) The Control Room indices to the Operating Procedure File did not reflect current revisions.
(2)
The procedure files did not denote the withdrawal of procedures and latest revisions to procedures were not available.
The licensee stated at the exit interview that the updated indices to Control Room Procedure Files and a verification of content o' files to match indices would be accomplished prior to July '.8, 1977.
This item will be reviewed at a subsequent inspection.
This is an unresolved item (77-28-04).
4.
Damaced Buildinc Soray Pumo Motor Bearinas On June 28, 1977, during the perforrance of the preoperational test TP 204/3, Reactor Building Spray System, the Building Spray Pump 1 A was started.
After a period af five minutes run time, observation by the Startup Test Engineer noted smoke emitting from the pump drive motor bearings temperature probes.
The pump was secured.
Initial investigation appeared to isolate the problem to an im-proper oil level in the motor bearings.
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The licensee's corrective action, retesting, and evaluation of future surveillance to prevent rectrrence will be reviewed at a subsequent inspection. This item is unresolved (77-28-06).
5.
Test Results Evaluation The inspector's review of the test results of the TP 257/3 (MTX 169.3) Service Air System included:
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Review of all test exceptions;
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b.
Review of test deficienc'es; (
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a
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c.
Review of the " cognizant engineering review" which was accom-plished on June 20, 1977; and, d.
Test results were approved by the Test Working Group on June 30, 1977.
Independent calculations were made to verify licensee's test re-sults.
fio inadequacies were identified by the inspector.
This item is closed.
6.
Hot Functional Test Procram Review (HFT)
The licensee has scheduled the start of Hot Functional Test for July 21,1977. A period of thirty days to complete testing is anticipated. The master procedure SP 600/28 Controlling Procedure for HFT (Draft), and support procedures TP 600/3 (MTX 147.10) Soluble Poison Concentration Control Test -
Approved March 9,1977, TP 600/10 (MTX 147.11) RCS Hot Leakage Test - Approved March 16, 1977, TP 600/11 (MTX 59.8) Emergency Feed System and 0TSG Level Control Test - Approved March 16, 1977, TP 600/13 (MTX 147.12) Pressurizer Operational and Spray Flow Test - Approved May 12, 1977, TP 600/30 (MTX 147.7) HFT Checkpoints - Approved May 12, 1977, have been reviewed to ascertain that tests are consistent with
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Regulatory Requirements and licensee commitments.
Items verified included prerequisites including the requirements that operating procedures have been approved, cold functional testing results have been reviewed for status to support testing, documentation of sequencing of testing (detailed test sequencing diagram), hold points have been addressed to require engineering evaluation prior to change in test plateau (temperature / pressure changes), water quality, and test criteria established.
The therral pipe expansion and pipe hangers have been addressed in the test program.
Specific heatup/cooldown rates have been established.
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Areas of concern have been discussed with the licensee.
Comments are as noted below.
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a.
TP 600/3 - Soluble Poison Concentration Centrol Test (1) Acceptance Criteria
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The various boration and deboration tests require the comparison of calculated results to the actual chemical analysis results.
No definitive criteria of acceptable span of concentration is documented.
Pending licensee establishment of the acceptance criteria, this item is unresolved.
(77-28-01)
(2) Operatino Procedure The test referenced operating procedure (2103-1.2).
This procedure does not address emergency baration.
This item is unresolved.
(77-28-02)
b.
SP 600/28 - (Draft) Controllino Procedure for HFT The controlling procedure fails to identify the concurrent test SP 365/2 - Loose Parts Monitor Baseline Data Acquisition.
Pending licensee revision to program this item is open.
(77-28-03)
c.
TP 600/13 - Pressurizer Ooerational and Soray Flow Test The TP 600/13, Section 9.5 in which the pressurizer spray valve flow is set at 190 + GPM.
The RCS condition for test are 1400 1 25 psig and 532 1 5 F.
The licensee has identified these conditions as a departure frcm limitations and pre-cautions for maintaining fuel cladding in compression (similar test to run after core loading). The NSSS has proposed a relaxation of DP 1101-01 limitations for temperature pressure conditions during BOL conditions.
Pending licensee submittal to NRR and its concurrence to relaxation of limitations, this ite'm is unresolved.
(77-28-07)
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Drawdown Test References:
(a) Report 10 CFR 50.55(e) Arnold /Knuth, June 27, 1975
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(b) Letter Babcock & Wilcox/GPU Service Corporation May 8, 1975 (c) Final Safety Analysis Report, Question 310.4/
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(d) Test Procedure 204/3 - Reactor Building Spray
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System Functional Test
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The MSSS identified (reference b) a potential prob'iem area to the licensee concerning the operation of the Reactor Building Spray System in the area of drawdown times in the Lodium hydroxide, sodium thiosulf ate and borated water storage tanks.
The FSAR (reference c) has been amended in submittal 48 (November that addressed the elimination of sodium thiosulfate use 15, 1976)
and changed the spray system to use sodium hydroxide iniection.
Other items of concern were addressed in section 6.2.3 in the area A revision to of Containnent Air Purification and Cleanup System.
test abstract TP 204/3 was also addressed in Amendment 48.
The licensee has completed portions of the test that verify draw-A final report is to be submitted to NRR to close the 10 CFR down.
50.55(e).
The data is presently being reviewed by the licensee and will be available for results evaluation onsite.
Pending review of test data, this item is unresolved.
(77-28-05)
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TP 600/20 - Loss of Electric Power Test During the inspector's review of procedures approved for perfor-
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mance during the Hot Functional Test Program, the licensee identi-fied a potential reportable item under 10 CFR 50.55(e).
The licensee stated that a possible design deficiency relating to the design of the reactor coolant pump seals and their cooling The seals presently are not designed to accept, water supply.
without possible damage, the thermal transient that could occur during station blackout and subseque' t reinitiation of cooling flows.
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Pending the resolution of this design deficiency and approval of the preoperational test procedure TP 600/20, this is an unresolved item.
(77-28-06)
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Observation of Physi ~ cal Plant _
The inspector walked through work areas 6n a daily basis and observed work activities in the control room, main steam generator, RC pump areas, NDT in progress on RC system, diesel generator wiring verifications, radwaste areas, makeup pump rooms, and
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turbine building.
No inadequacies were identified.
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10.
Exit Interview At the inspection's conclusion on July 1,1977, the inspector held a meeting to discuss the inspection scope and findings.
The unresolved and open items were identified.
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