IR 05000320/1976017
| ML19220B552 | |
| Person / Time | |
|---|---|
| Site: | Crane |
| Issue date: | 12/22/1976 |
| From: | Mccabe E, Rebelowski T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220B549 | List: |
| References | |
| 50-320-76-17, NUDOCS 7904270020 | |
| Download: ML19220B552 (10) | |
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-IE:I Form 12 (Ja-75) (Rev)
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U. S. NUCLEAR RECUL\\ TORY CC'CIISSIO:i OFFICE OF INSPECTION AND ENFORCCiE:
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REGION I
IE Inspection Report No: _
50-320/76-17 Docket No:
50-320 Licensee: _
Metropolitan Edison Cenpany g
g CPPR-66 Box 542
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Priority:
Reading, Pennsylvania 19603
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Safeguards Location:
Middletown, Pennsylvania (TMI-2 Type of Licensee:
Type of Inspection: _ Routine, Unannounced t
Date= of Inspection: _
November 10-12, 1976
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Dates of Previous litspection:
October 13, 14-21, 1976 Reporting Inspector: \\
t T. Rebelow
, Reactor inspector ff // //M DATE Accompanying Inspectors:
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DATE Other Accompanying Personnel: _
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DATE Reviewed By: _
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b2h h E. C. McCabe, Jr., Section Chief, Nuclear Support t a /'A s /7 t Section No. 1, RO&NS Branch DATE
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SUKd.ARY OF FINDINGS Enforcement Action
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None Licensee Action on Previously Identified Items
Not inspected.
),esign Changes Not inspected.
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Unusual Occurrences Fire in Non-Saf etv-Related ' Area 1.
A fire occurred in a temporary pre-fabricated structure on the evening of November 11, 1976.
(Detail 6)
2.
Cooling Tower Da= age f
A Unit 1 Mechanical cooling Tower fan #3 dislodged a blade causing damage to the uptake plenum of unit.
(Detail 7)
Other Significant Findings _
Accentable Areas A.
(These are areas which were inspected on a sa=pling basis and findings did not involve an Ites of Nonccmpliance or an Unresolved Item, except as noted in the Unresolved Itms section of this report.)
Observation of Flush of Nuclear Closed Cooling Water System.
1.
(Detail 3)
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Review of Preopet
' al Test Procedures.
(Detail 4)
(Detail 5)
3.
Inspection of Diesel Rooms and Fuel Storage area.
Unresolved Items _
B.
(These are areas on which further review or more infor=ation is the items are acceptable.)
required to determine whether or not
- 76-17-01 MTX 110.4 Results Review (Detail 3.a(7))
- 76-17-02 Flush Diagram Update (Detail 3.b(1))
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- 76-17-03 Increase of Flushing Temperature (Detail 3.c(8))
- 76-17-04 R. B. Hydrogen Control - Tes t Duration (Detail 4.b)
- 76-17-05 Cable Temperatures (Detail 4.c(2) (a))
- 76-17-06 Full Load Test Duration (Detail 4.c(2)(b))
- 76-17-07 Diesel Starts (Detail 4.c(2) (c))
- 76-17-08 Air Solenoid Starts (Detail 4.c(2)(d))
- 76-17-09 Diesel Trips (Detail 4.c(2) (e))
- 76-17-10 Operational Procedures (Detail 4.c(2)(f))
- 76-17-11 First-Out Failures (Detail 4.c(2)(g))
- 76-17-12 Maintenance Exercise Switch Position (Detail 4.c(2)(h))
- 76-17-13 Review of Fire Protection Diesel Rm (Detail 4.c (2) (1)
- 76-17-14 Building Fire Review (Detail 6)
C.
Status of Previousiv Unresolved Items Not inspected.
Management Meeting A management entrance meeting was conducted with Mr. R. Toole, Test Superintendent, on November 10, 1976. The inspector su=sarized the purpose and scope of inspection.
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At the conclusion of the inspection on November 12, 1976, a management exit meeting was held onsite with the following personnel in attendance:
Mr. R. Fenti, QA Auditor, GPUSC Mr. T. Hawkins, Assistant Startup Test Superintendent Mr. S. Levin, Proj ect Engineer Mr. P. Levine, QA Auditor
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Mr. M. Nelson, Technical Engineer The following st==arizes the items discussed:
A.
Preoperation Test Procedure Review (Detail 4)
B.
Observation of Flushing in Progress (Detail 3)
C.
Observation of Diesel Generator Rooms and Fuel Storage Area (Detail 5)
D.
Unit I Mechanical Cooling Tower Fan Failure (Detail 7)
E.
Prefabricated Building Fire Damage (Detail 6)
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Persons Contacted General Public Utilities Service Corporation (GPUSC)_
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Mr. J. Barton, Startup and Testiig Manager Mr. R. Fenti, OA Auditor Mr. T. Hawkins, Assistant Startup Test Superintendent Mr. S. Levin, Proj ect Engineer Mr. P. Levine, QA Auditor Mt. M. Nelson, Technical Engineer Mr. R. Toole, Test Suoerintendent United Engineers and Constnietors, Inc. (UE&C)
Mr. B. Kaufer, Startup Engineer Mr. D. Rhyne, Group Leader Mechanical Engineer Mr. G. Schmidt, Piping Supervisor 2.
Purpose and Scone of Inspection The inspection purpose was to witness preoperational flushes of saf ety-related piping and review preoperational test procedures.
The inspection included a tour of the Diesel Rocus, the Fuel Storage Area, the Control Room and the Nuclear Closed Cooling Water Service Areas.
Flush of Nuclear Services Closed Cooline Water System (NSCC)
3.
The inspector observed the flushing in progress for those a.
portions of NSCC that have been released for Phase 1 testing.
The documents reviewed by the inspector to verify readiness for flush included the following:
(1) Phase I Turnover Agreement.
(2) Piping exception list.
(3) Nuclear Services Closed Cooling Flush on Procedure TP 250/4 MDC 110.4.
(4) FSAR - Art. 9.2.2.3.
(5)
QC-11-2, Rev. 2, Cleaning and Cleanliness Control.
(6)
QC-21-2, Rev. 2, Flushing of Piping Systems and Co=ponents.
(7) ANSI N45.2.1-1973.
(8) Three Mile Island Test Manual.
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Documentation Review The results of the inspector's review of the above listed docu=ents are noted as the following two areas of concern:
(1) The licensee has not established a uniform method of docu=enting completed flushes from original flush PID to the updated revision at the time of flush.
Presently, the project engineer in charge of the NSCC flush is re-marking diagrams for the syste=s involved.
The inspector stated that a method that would encompass flush update to the latest piping plan revisions is necessary.
The licensee stated that this item would be reviewed. This item is unresolved.
(76-17-02)
(2) The inspector asked about the method by which the systems under flush are properly supported.
The licensee stated that all dead load hangers are in place and that additional te=porary hangers are added to piping systems, during pre-inninary flushing operations, by the system engineer and piping supervisor based en walk thru observations. Missing hangers were documented in MTI 110.4 and inspector obser-vation of piping under flush identified no vibration ab-
normalities.
The inspector had no further questions in this area.
Additional areas documented by the licensee included the specified flow paths to assure sequential cleaning where possible, sa=nle point analysis of initial and final flush water system flow, valve alignment, test engineer verification and Q.C. verification of flushing results.
The inspector identified no inadequacies in the above additional areas.
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Witness of Flush NSCCWS The inspector's observation of flushing operation of NSCCWS i
verified the following:
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(1) Proper procedure and data sheeta were at the test area.
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Instru=entation used to determine flushing velocities were calibrated.
(3) No test changes were required.
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(4)
Criteria for cleanliness was stated in the procedure.
(5)
Quality Assurance notification of systems under flush was docu=ented.
(6) Discussions with the project field engineer indicated system knowledge and familiarity with the flushing methods and procedures.
(7) Flush strainers are installed at suction of system pumps.
Criteria for AP across suction strainers is docu-mented.
The system presently is under flush for about 10 days and does not presently =eet cleanliness require-The test results will be reviewed during a sub-ments.
sequent inspection.
This item is unresolved.
(76-17-01)
(8)
The flush vater temperature entering the HX was indicating 38 F.
The ability to clean system piping and the possibility
,f condensation in secondary sections of E2 was discussed.
The licensee stated that system flushing medium te=perature will be raised.
This item is unresolved.
(76-17-03)
4.
Preoperational Test Procedure Review I
The inspector reviewed the following approved preoperational a.
test procedures.
T P 160/4, Reactor Juilding Hydrogen Control Test.
T P 401/1, Diesel Generator Functional Test.
Review included the Final Safety Analysis Report recuirements, system operatienal requirenents, appropriate management approval,
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format, test objectives, prerequisites, acceptance criteria, initial plant conditions established, adequacy of references,
l stepwise sequential instructions, appropriate data collection provisions, step verification and test personnel identification, i
i system restoration, and applicable Q.C. verification.
b.
T.P. 160/4 Reactor Building Hydrogen Control Functional Test The test procedure addresses system ability to control Reactor Building discharge flow rates and verification of supply and discharge valve interlocks with the Reactor Building Hydrogen Control Exhaust Fan.
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The duration of The inspector identified one area of concern.The licensee stated that a fan operation is not addressed.
mini =um operating time will be included in procedure prior This item is unresolved.
to approval for performance.
(76-17-04)
T.P. 401/1 Diesel Generator Functional Test c.
The Diesel Generator Functional Test addresses operational (1)
verification of the following.
Diesel generator operation including remote manual (a)
and local manual starting to demonstrate the capability to attain and stabilize frequency and voltage.
Diesel fuel oil system operation including the day (b)
tank level control.
(c) Diesel generator fuel oil consumption.
Air starting system operation including air reservoir (d)
pressure control.
Five successive starts of the diesel generator with-
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out recharging the air starting system.
(f) Overspeed Trip.
(g) Start Failure.
Ability of diesel generator to start and be at 900 RFM (h)
and ready for loading in ten seconds or less after start initiation.
Voltage control of the exciters in both manual and (i)
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auto modes.
Capability of rejecting the maxi =um rated load.
(j)
The inspector identified the following concerns.
(2)
there are no current provisions The inspector acted that (a)
for monitoring temperature of cables in overhead trays C
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during the full load test of diesel to ensure that temperature rise of energized cables are within acceptable limits.
This item is unresolved.
(76-17-05)
(b)
Diesel full load testing for one hour is planned.
Such testing meets the licensee's commitment.
The NRC recoc= ended test program now specifies 6-10 hours of full load testing.
This ites, 76-17-06, will receive further NRC review.
(c) Eleven diesel starts are planned. This testing meets the licensee's coemitment (FSAR Supplement 2 Question 22.20).
The NRC recommended test program new specifies 35 test starts.
This item, 76-17-07, will receive further NRC review.
(d)
The inspector noted that each individual air starting solenoid valve is not testing.
tested independently during The licensee stated that this item will be included in a procedure revision.
(76-17-08)
This item is unresolved.
(e)
The inspector asked the licensee to clarify the ite=s that would trip the diesel.
The licensee stated that trips were discussed with NRR and that the circuitry would reflect the regulatory position. The review of changes to the circuitry will be inspected at a subsequent inspection.
item is unresolved. (76-17-09)
This (f)
The inspector noted that the performance of operational procedures are not addressed as references in the test procedure.
The licensee stated that, operational procedures would be performed prior toupon com fuel loading. This item is unresolved.
(76-17-10)
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-8-(g) The inspector asked about the ability to recognize cause of diesel failures (First out trip).
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licensee stated that the numerous indications available atthe ability is available b
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the annunciator panels.
licensee's operations departmentThis unresolved item w inspection.
(76-17-11)
during a subsequent (h)
The diesel control " Maintenance Exercise" functio was reviewed.
(ES) signal vill not startIn this mode an Engineered S guards The inspector questioned whether the diesel shan idle diesel.
breakers are racked out to permit mainten ould Currently, the circuitry meets the commitment
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established.
This item, 76-17-12, will receive s
further NRC review.
(1)
The diesel room was exa=ined and a nu to the diesel fuel storage areas were=ber of openings cation received by the inspector indicated that noted.
Infor-openings were for ventilation and that automati these closure of openings in case of fire is accompli h d l
c by a Type A Fire Door that is activated at
se of 1600F.
Doors and the fire detection devices in DiThe re a temperature e
Rooms was not addra.ssed.
esel Generator (76-17-13)this unresolved ites during a subseqThe inspector uent inspection.
5.
Inspector's Tour Area, Control Room and observed selectedThe insp ooms, Fuel Oil Storage installation and flushing instrumentatiClosed Cooling umps, EX and secainer on.
Nuclear Services River Water temperatThe inspector r temperatures were approaching inspected for hanger installati ures (380F).
The areas were l
(Details 3).
Specific inspection concerns are addron to support flushing j
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_ Prefabricated Building Fire essed in Detail 4.
A small fire was found during guard r
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near Unit 2 construction site. Preliminary investigation by theounds C
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licensee determined that a f aulty thermostat was the cause. The inspector noted licensee's removal of charred areas. Problems were encountered with fire companies entrance to site and adequacy of available firefighting equipment. This ynresolved item (76-17-14)
vill be documented in NRC:I Inspection Report 50-320/76-18.
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Mechanical cooline Tower Fan Blade Dislodeement At 10:15 hours, November 11, 1976, a blade from the "C" f an of Mechanical Cooling Tower, Unit 1 was dislodged. The f an blade, one of eight per f an, had sheared the bolts of the blade clamus and the clamp fasteners, and was thrown through the fan cylinder which directs air discharge. The inspector observed initial tower vibration and the results of blade loss.
The three f ans of the mechanical cooling tower were secured until the licensee determined which fan had failed. The tower was returned to service and maintained the T.S. limits as to acceptable discharge te=perature of < 2 F.
Discussions with the operations supervisor indicated that the problem of the loss of blade had occurred previously.
The unit is a class 600 Doubla Flow Tower. The failure of the vibration monitor at the motor drive was not addressed by the licensee. This item will be reviewed at. a suosequent inapection.
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