ML19322D929
| ML19322D929 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/05/1978 |
| From: | Kirk I NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA) |
| To: | NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA) |
| Shared Package | |
| ML19322D920 | List: |
| References | |
| NUDOCS 8003110229 | |
| Download: ML19322D929 (3) | |
Text
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t' Reference 27 O
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UNITED STATES y*
NUCLEAR REGULATORY CCMMISSION
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JUL 5 573 Those on Attached 1.ist COMPUTER LISTINGS OF LICENSEE EVENT REPORTS-SORTED-BY FACILITY The enclosed computer listing provides infonnation concerning licensee event reports entered into the file during the month of June.
If you desire additional information or special searches, please do not hesitate to conta:t us.
//c/Ns, /b ks.
I. A. Kirk, Chief s
Automated Systems Branch Division of Technical Support Office of Management and Program Analysis
- b. closure:
As stated 9
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soosi to 22k
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e JUN 30. 1978 LER MONTHLY OUTPUT SORTED BY. FACILITY PAGE 63 PROCESSED DURIHC JUNE Fod POWER REACTORS FACILITY / SYSTEM / COMP 0HENT/
DOCKET N0./
EVENT DATE/
1 COMP 0HENT SUDCODE/CAUSE CODE / LER HO./
REPORT DATE/
EVENT DESCRIPTION /
CAUSE SUDCDDE/ MANUFACTURER CONTROL HO.
REPORT TYPE CAUSE DESCRIPTION J
05000320
)42378 IN MODE 1 REACTOR TRIPPED FROM 30N R.T.P.
RCSRAPIDLYCOOLEDDOWNINGD THREE MILE ISLAND-2 f
p HAIN STEAN SYSTEMS
- CONTROL 78-033/OlT-0 C,/878 EPRESSURIZED. DURING DEPRESSURIZATIDH. SAFETY IHJECTIDH WAS IHITIATED.
VALVES 021273-2-WEEK kCS AND PRESSURIZER C00LDOWN RATES WERE EXCEEDED (T.S. 3.4.9.1 AND 3.4.
OTHER 9.2).
PRE 55URIZER VOL DELOW LIMITS OF T.S.
3.4.43.
CALCULATIONS AND RA DESIGN /FADRICATION ERROR DI0 CHEMISTRY SHOW THAT CORE REMAINED COVERED AT ALL TIMES AND HD RELEASE CCHSTRUCTICH/INSTALLATIDH OF RADIOACTIVE MATERIAL RESULTED.
ITEM HOT APPLICADLE Y.
FOLLOWING RX TRIP. HAIN STEAM RELIEF VALVES DID HOT RESEAT AT CORRECT PR
^*
ESSURE.
FEEDWATER SYSTEM RESPONSE SLOW,SINCE IHITIAL INTEGRATED CQHTROL SYSTEM TESTING STILL IN PROGRESS. COMBINATION OF' RELIEF VALVES FAILING TO RESEAT AND CONTINUING TO FEED STEAM GENERATOPS RESULTED IN RAPID DEP1 RESSURIEATIDH AND C00LD0yH.
RVS WILL DE TESTEQ.
THREE MILE ISLAND-2~
0S000320 042478 IN MODE 1 REACTOR TRIP CAUSED SEVERAL MAIN STEAM RELIEF VALVES.10 LIFT.
MAIN STEAM SYSTEMS + CONTROLS 78-034/08T-0 050878 DUE TO INADEQUATE DESIGH. SEVERAL STEEL LIHERS USED TO PRUTECT Tite DELL a
' VALVES-021272 2-WEEK OWS IN THE DISCHARGE PIP (HG WERE EJECTED. DECAUSE Tills WAS ON SECONDARY OTHER SIDE OF THE PLANT. AND HQ RADIATION WAS RE8. EASED. EVENT POSED HD THREAT
. DESIGN /FADRICATION ERROR 10 Til E il[ALTH AND SAFETV 0F THE PUBLIC.
DESIGH ITEM 140T APPLICABLE THIS EVENT WAS CAUSED DY AH IHADEQUATE DESIGH WilICH ALLOWED THE USE OF B ELLOWS LINERS QUALIFIED P,0R 180 F/SEC. STEAM VELOCITY IN A LOC ATION WilER E VELOCITIES UP TO 950 F /,S E C. COULD DE EXPERIEHCED.
THE UNDER-DESIGHED DELLOWS LINERS ARE DEIHO REPLACED DY LIN,ERS OF AN APPROPRIATE DESIGH.
THREE MILE ISLAND-2.
05000320 050378 IN MODE 5 DURHS & ROE NOTIFIED MET *ED THAT S!HGLE AUXILIARY TRANSFORMER SYSTEM CODE HOT APPLICADLE 78-035/01T-0 050978 OPERATIOlt WITilIN THE HORHAL OPERATING RANGE of Tile GRID WILL NOT PROVIDE COMPollENT CODE NOT. APPLICABLE 02127I 2-WEEK SUFFICIENT VOLTAGE LEVELS FOR OPERATION OF THE 480'V MOTOR COHTROLLERS SUBCOMPONENT NOT APPLICABLE DURING PERIODS OF PEAK UNIT AUXILIARY DEMAHD. UNIT HAS HOT OPERATED AT OTilE R A P0HER LEVEL REQUIRING MAXIMUM Uti!T AUXILIARIES. HQ POTCHTIAL Fs0R ADVE NOT APPLICADLE RSE EFFECT OH THE HE ALTil AND SAFETY OF Tite PUBLIC.
ITEM HOT APPLICADLE A/E SHOWED THAT WITHIH HURM4L RANGE (232 TO 238KV) OHE TRANSFORMER CAN'T PROVIDE ADEQUATE VOLTAGE LEVELS TO SUPPORT OPERATION OF ENGIHEERING SAF ETY FEATURES AND BALANCE OF PLANT AUXILIARIES.
TitREE' POSSIBLE CORRECTIV E ACTIOHS EXIST.
TROJAH-1 05000344 032578
'WHILE IN COLD SHUTDOWN WI'TH THE REACTOR COOLANT SYSTEM' PARTIALLY DRAIHED FLOW WAS DElt4G SUPPLIED BY ONE RESID.UAL llEAT REMOVAL (RHR) PUMP.
ON T RESIDUAL HEAT REMOV SYS + COHT 78-Ott/03L-0 042478 INSTRUMENTATION + CONTROLS U28197 30-DAY.
WO OCCASIGHS-(MARCH 25. 1978 Al4D APRIL 17. 1970) RCACTUR C00LAHT SYSTEM FLOW HAS LOST HHEH REACTOR VESSEL HATER LEVrt IHADVERTEHILY DROPPl:D lif t p INDICATOR PERSOHHEL ERROR W THE Poll 4T W14 E R E Tile RHR PUMP TAKES'IIS SUCIIGH.
LICENSED & SLHIUM UPLRAluRS DARTUN INSTRO Co.
DIV UF I t '!
g THE CAUSE OF THESE EVENTS IS ATTRIDUTED TO INSIRUHLHT ERROR.
Il4 IllE NAR CH 25 EVENT A. PRESSURE GAUGE WAS OUT OF CALIHRATION WillCal RESUL TED IN AH ERRONEOUS LEVEL INDICATION.
IN THE APRIL 17 EVENT THE LEVEL Its THE REF-
-FRENCE LEG OF THE LEVEL INSTRUMEllT HAS LOW CAUSING II 10 READ INC.O R RI C T L V.
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- ) S REGION I Reference 31 E 'h f
531 PAXK AVENU3 D
90tiO OF FRttS51A. POf MSYt.VANI A 11 V
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SEP 211978 i
Docket No. 50-320
[..
Metropolitan Edison Company I.
ATTH:
Mr. J. G. Herbein Vice President - Generation
[
P. O. Box 542 Reading, Pennsylvania '19603
[..
j:
Gentlemen:
Subject:
Inspection 50-320/78-28 This refers to the inspection conducted by Mr. D. Haverkamp of this office o'n September S-7,1978 at Three Mile Island Nuclear Station, Unit L-2, Middletown, Pennsylvania, of activities authorized by NRC License No.
~
OPR-73 and to the discussions of our findings held by Mr. Haverkamp with i
Mr. J. Seelinger and other member of your staff at the conclusion of the inspection.
5 Areas examined during this inspection are described in the Office of f
Inspection and Enforcement Inspection Report which is enclosed with this letter. Within these areas, the inspection consisted of selective s
examinations of procedures and ' representative records, interviews with personnel, and observations by the inspector.
Within the scope of this inspection, no items of noncompliance were i
observed.
In accordance with Section 2.7S0 of the NRC's " Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the
~
enclosed inspection report will be placed in the NRC's Public Document Room.
If this report contains any information that you (or your contractor)
~
believe to be proprietary, it is necessary that you make a written application within 20 days to this office to withhold such information from public disclosure. Any such dpplication must be accompanied by an F
affidavit executed by the owner of the information, which identifies the F
document or part sought to be withheld, and which contains a statement of reasons nich addresses with specificity the items which will be considered by the Comission as listed in subparagraph (b)(4) of Section 2.790.
The information sought to be withheld shall be incorporated as far as possible into a' separate part of the affidavit.
If we do not hear from you in this regard within the specified period, the report E
will be placed in the Public Document Room.
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Metropolitan Edis';n Company 2
SEP 211978
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No reply to this letter is required; however, if you should have any questions concerning this inspection, we will be pleased to discuss them with you.
Sincerely, 1o
' Brunner, Chief Reac'wr Operations and Nuclear Sdpport Branch
Enclosure:
Office of Ir.spection and Enforcement Inspection Report Nt:rber 50-320/78-28 cc w/ encl:
T. Broughton, Safety and Licensing Panager J. J. Barton, Project Manager R. C. Arnold, Vice President - Generation L. L. Lawyer, Manager - Generation Operations - fluclear G. P. Miller, Superintendent J, L. Seelinger, Unit 2 Superintendent - Technical Support I. R. Finfrock, Jr.
Mr. R. Conrad G. F. Trowbridge, Esquire f
Miss Mary V. Southard, Chainr.an, Citizens for a Safe Environment (Without Report) bec w/ enc 1:
IE Pail & Files (For Appropriate Distribution)
Central Files Public Doctcent Rooa (PDR)
Local Public Documa.nt Room (LPDR)
Nuclear Safety Infonr.ation Center Technical Infonation Canter (TIC)(tiSIC) s REG:I Reading Reca Region Directors (III, IV)(Report Only)
Comonwealth of PennsyIYania s
Miss Mary V. Southard, Chainran, Citizens for a Safe Environment
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.OM e M L
D'.S. NUCLEAR REGULATORY COMMISSI'Os
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0FFICE OF INSPECTION AND ENFORCEMENT Region I NOTICE Report No. 50-320/.78-28 2 1 SEP 1978 M OF Docket No* 50-320 REGION i HAS NOT OBTAINED PROPRIETARY
{l CLEARANCE IN ACCORDANCE YSTH 10 CFR 2790 i
License No. DPR-73 hiority Category i
B2
~~
Licensee:
Metropolitan Edison Comany f'
l-P.O. Box 5?2 Reading, Pennsylvania 19603 E
Facility Name:
Three Mile Island Nuclear Station, Unit 2 5:
Inspection at:
Middletown, Pennsylvania Inspection conducted: Septem! _r 5-7, 1978 1
Inspectors:
[de 9[/P[78 D. R. Haverkarnp, Reactf/ Inspector date signed date signed S
date signed
~
Ap; roved by:
12 /
8 /3 8
[ R. R. M, Chi eactor Projects
/date signed Sectio, ao.1, -,gdBranch Insoection Sur: nary:
Insoection on September 5-7,1978 (Report No. 50-320/78-28)
Areas insoected:
Routine, unar.nounced inspection by a regional based inspector of SIS reset feature; licenses followup actions concerning selected previous inspection findings, licensee events and IE Bulletins and Circulars; and selected licensee special reports. The inspection ir.5olved 22 inspector-hours onsite by l
one NRC regional based inspector.
Resul ts:
No iteras of nonccepi4ance were identified.
?
DUPLICATE DOCUMENT I-Entire document previously entered into system under:
r' ANO '[h / l h
Region I Form 12 N
f Pages:
(Rev. April 77)
U
(
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r DETAILS 1.
Persons Contac'M Metrooolitan Edison Comoany Mr. R. Sensel, Unit 2 Lead ' Electrical Engineer
- Mr. M. Bezilla, Unit 2 PORC Secretary
- Mr. J. Floyd, Unit 2 Supervisor of Operations Mr. J. !!ilbish, Station Lead Nuclear Engineer Mr. B. Mehler, Shift Supervisor Mr. I. Porter, Unit 2 Lead Instrumentation ~ and Controls Engineer.
- Mr. J. Seelinger, Unit 2 Superintendent-Technical Support Mr. R. Warren Unit 2 Lead Mechanical Engineer General Public Utilities Service Corocration Mr. W. Gunn, Site Project Manager Mr. R. Toole, Test Superintendent Mr. J. Wright, QA Manager The inspector also interviewed several other licensee and contractor exployees during the inspection.
They included control room operators, technical and engineering staff personnel and general office personnel gr i
- denotes those present at the exit interview on September 7,1978.
2.
Licensee Action on Previous Inscection Findinos (Closed) Unresolved Item 320/77-29-02:
Fuel component and material certi fica tions. A licensee representative stated that these records re..ain stored at the GPU offices in Parsippany, New Jersey. The inspector acknowledged the availability of the records for future NRC review and had no further questions concerning this item.
(Closed) Ncncorpliance 320/77-47-09:
Installaticn of pipe supports in ' variance with detail drawings.
The licensee's corrective measures were cocpleted as described in MEC letter to Region I, serial GQL 0433, dated March 16,1978.
The inspector had no further questions concerning this item.
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- f. Closed) Noncompliance 320/78-12-01:
Welding of anchor plate studs without an approved welding procedure. The licensee's corrective measures were cocpleted as described in MEC letter to Region I, serial GQL 0811, dated May 1,1978.
(
Reference:
NRC Inspection 3
Report 50-320/78-15, paragraph 2.) The inspector had no further questions concerning this item.
(Closed) Nonco::pliance 320/78-20-01:
Failure to verify equipment hatch closed and sealed.
The licensee's corrective actions were cc::pleted as described in HEC letter to NRC Region I, serial GQL 1108,. dated June 20, 1978.
The inspector reviewed Surveillance i
Procedure 2301-M8, " Containment Integrity Verification," Revision 5, dated June 12, 1978.
The revised procedure includes requirecents l.
to verify that the equipment hatch is closed and sealed. _The in-spector had no further questions concerning this item.
(Closed)
Unresolved Item 320/78-20-02: LLRT' procedure items.
The inspector reviewed SP 2313-R7, " Reactor Building Local Leak Rate i
Testing," Revision 1, dated July 19, 1978.
The revised procedure includss appropriate changes / provisions for (1) quantifying test i
boundary valve leakage vice CIV leakage, (2) taking flowmeter i
readings after both pressure and flow stabilization, (3) ensuring i
instricentation is traceable to NBS stanc'ards, (4) operating the test rotameter and LLp,T test stand and associated valves, (5) y 4
^
deleting references to superseded items (stsps 5.2 and 7.3) and (6) specifying applicable minimum sensitivity values.
In addition, TCN's P. ave been initiated for SP 2313-R7, SP 2311-5, and SP 2303-SAZ to ensure that all applicable test results are included in the total combined leakage rate of penetrations and valves subject to Ty.e 3 and C tests.
(Closed) Ncncocpliance 320/78-20.03:
Improper air lock door seal test. The licensee's corrective measures were completed as described in MEC letter to NRC Region I, serial GQL 1108, dated June 20, 1 978.
The inspector reviewed SP 2311-5, " Containment Integrity",
Revisica 3, dated June 12, 1978.
The revised procedure requires testing of the air lock door seals using a rotameter type flowmeter, which is.censistent with recently revised Technical Specifications for conducting th'is test.
The inspector had no further questions concerning this itsa.
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(Closed) Honcompliance 320/78-20-04:
Failure to implement sur-
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yet11ance procedures for air lock door seal testing.
The licensee's corrective measures were completed as described in MEC letter to
~
NRC Region I, serial GQL 1108, dated June 20, 1978.
The inspector reviewed ccmpleted surveillance procedures SP 2311-5, " Containment Integrity," Revisions 3 and 4, performed during June 15-August 31, 1978. Required data were correctly entered in these procedures.
Additionally, the licensee's method of identifying TCN's in the body of the control room file and working copies of procedures has been satisfactorily implemented.
Tne inspector had no further ques-tions concerning this item.
(Closed) Noncompliance 320/78-20-05:
Failure of employees to monitor themselves when leaving a controlled area. The licensee's corrective measures were completed as described in MEC letter to NRC Region I, serial GQL 1108, dated June 20, 1978.
All operators have reviewed the requirements of HPP 1612 and SP 2311-5. The inspector inter-viewed selected operators and determined that they were knowledgeable of the proper procedure for gaining access to the air lock door seals for surveillance testing.
The inspector had no further questions concerning this itea.
(Closed) Unresolved Item 320/78-20-06:
Isolation of pressure source by a single root valve during pressure decay tests.
The licensee's method of measuring air lock sea? leakage has been changed from a y~
pressure decay test to a rotameter type flow test.
Additionally, when pressure decay is used as a measurenent of other leakage rates, the pressure source is disconnected.
The inspector had no further questions concerning this item.
(Closed) Unresolved Itea 320/78-20-07: Guidance on sequence of seal leak test and door closure.
The inspector reviewed SP 2311-5, " Con-tainmnt Integrity," Revision 4, dated July 12, 1978.
The revised procedure requires testing the inner door seal and then the outer door seal of both air locks.
These tests are accomplished without opening any door after the test.
The inspector had.'.c further ques-tions concerni'ng this item.
(Closed) Unresolved Item 320/78-20-08: Bypass leakage.during air lock test. The inspector reviewed SP 2303-SA2, "RB Hatch Leak Rate and Interlock Test," Revision 1, dated July 26, 1978, and TCN 2-78-580.
The TCN requires use of a modified test pressurization rig which isolates and vents the flowmeter bypass line during air lock leak testing.
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5 (Closed) Inspector Followup Item 320/78-23-01:
Pipe restraint deficiencies. The loose steel support plate near mechano al snubber 863 and tk.e excessive attachment angle of mechanical snubber 411 were corrected by Catalytic work authorization !809.
While perfor:: ling this work, snubber 411 was found to be bound up and was replaced witr snubber 2459. The inspector observed the completed maintenance and had no further gJestions' concerning this item.
(Closed) Unresolved Itea 320/78-24-02: Heat treating procedure (draft) heating and cooling rates were greater than allowed by code req 1f recents.
The inspector reviewed the approved main steam piping post weld heat treat =ent procedure for FCR 2520.1, " Heat Trcating Procedure," (Original) dated July 18, 1978.
The procedure included appropriate heatina and cooling rates above 600 F, in confomance with re:uirements of the USAS 831.7 Code.
Additionally, the inspector reviewed selected QC inspection reports of actual heat treat: rent and detennined that identified deviations were satisfactorily resolved.
The inspector had no further questions concerning this ite:.
(Closed) Unresolved Ite. 320/78-24-03:
EDG low lube oil day tank level alarm cperability.
The apparently out of service annunciator alann was due tc a turned out light bulb, which was replaced.
Tne ins;ector verified the alara operability and had no further questions c
con:erning this iten.
(Closed) Unresolved Ites 320/78-24-04: Corrective measures for LER's 73-33/LT and 73-31/LT.
The inspector reviewed the results of rr.ain stsam safe y valve testing.
Each valve was checked for proper lift setting using a hydroset lift rig. Valve adjustments and additional tests were performed until satisfactory lift setpoints were attained. Selected valves were lift tested by slowly raising steam pressure, and the lift setpoints closely correlated with the hydroset test results. Appropriate blowdown ring positions were detar=fr.ed durir.g the steam pressure lifts, and each val'.M vas subsequently adjusted. The inspector verified that final tr.st results were acceptable and had no further questions concerning this ita7.
(Closed) Unresolved Ites 320/78-24-05: Update report for LER 78-44/3L. The licenses submitted Update LER 78-44/3L, dated August 24, 1973, wisich contained adequate narrative descriptions of the eye.t and the caus'e.
The licensee's corrective measures were satisfactorily cac:pleted, as described in Paragraphs 5 and 6 of this report.
Tr.e inspector had no further questions concerning this itea.
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pl 3.
SIS Reset Feature Review
,i The inspector reviewed the design capability for resetting a safety infection signal following a LOCA. The control system designs at certain other P'dR facilities include a SIS reset feature that, if actuated, would prevent proper ESF sequencing operation after a loss of offsite power following a LOCA. The emergency safeguards design at TMI-I includes a bypass function of each ESF actuation
~
circuit.
The ESF bypass functions and their effects are similar, but not identical, to the SIS reset function at other facilities.
The inspector reviewed the following Unit 2 emergency procedures.
EP 1202-6, "Less of Reactor Coolant / Reactor Coolant Pressure,"
Revision 7.
EP 1202-2 & 2A, " Station Blackout and Station Blackout with Loss of Both Diesel Generators," Revisio'n 9.
These procedures adequately control the insertion and removal of ESF bypass functions.
No items of noncongliance were identified.
4.
IE Bulletin and Circular Followuo T'
The inspector reviewed 'the' licensee's followup actions regarding the IE Sulletin and Circular listed below.
IE3 78-10, "Bergen-Patterson Hydraulic Shock Suppressor Accuaulator Spring Coils," dated June 27, 1978.
IEC 78-09, " Arcing of General Electric Company NEMA Size 2 Centactors," dated June 8,1978.
This review included discussions with licensee personnel, review of selected facility records, and observation of selected facility equipment and components.
With respect to the above Bulletin, the inspector verified that licensee runagement forwarded copies of the bulletin response to l
appropriate onsite management representatives, that information and l
corrective action discussed in the reply was accurate and effected as described, and,that the reply was submitted within the time period described in the bulletin.
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With respect to tha above Circular, the inspector verified that the circular was received by appropriate licensee management, a review i
for applicability was performed, and that action taken or planned if is appropriate.
Acceptance criteria for the above review included inspector judgement and recuirements of applicable Technical Specifications and facility precedures.
Licensee followup to the above Bulletin and Circular was acceptable.
5.
In-Office Review of Licensee Event Reoorts (LER's)
The LER's listed below were reviewed in the Region I office promptly following receipt e verify that details of the event were clearly F
reported including the accuracy of the description of cause and the adequacy of corrective action. The LER's were also reviewed to
~
determine whether further information was required from the licensee.
whether generic implications were involved, whether the event shculd be classified as an Abnormal Occurrence, and whether the event warranted onsite followup.
The folicr.<ing LER's were reviewed.
U;date LER 78-33/IT, dated July 31, 1978; Reactor trip followed by RCS depressurinti.on and sodium hydroxide injection, due to
- f steam generator safety valves not properly reseating.
c--
Update LER 78-34/IT, dated July 31, 1978; Cegradation of main steam safety valve discharge piping.
Update LER 73-44/3L, dated August 24, 1978; Manual output breaker G2-IE2 for the "A" diesel generator was not closed when the t: nit was placed in emergency standby, due to a procedure ir. adequacy.
LER 75-45/IT, dated July 19, 1978; Nonconservative calculational errors resulted in incorrect Technical Specification limits for variable pressure temperature trip and positive imbalances.
LER 78-48/3tf, dated August 22, 1978; A wall penetration in the "A" Ecergency Diesel Generator Building switchgear room was discovered to be lacking a fire barrier seal, due to an oversicht on the part of the contractor.
The above LER's were closed based on satisfactory review in the Region I office, except those LER's selected for onsite followup.
denotes those LER's salected for onsite followup.
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8 6.
Onsite t.icensee Event Follovuo For those 1.ER's selected for onsite followup (denoted in Paragraph 5), the inspector verified that the reporting requirements of Technical Specifications and G? 4703 (Original) had been met, that appropriate corrective action had been taken, that the event was reviewed by the licensee as required by Technical Specifications,
~
and that continued operation of the facility was conducted in con-fonrance with Technical Specification limits.
The inspector's findings regarding these licensee events were acceptabl e.
7.
In-Office Peview of Soecial Recorts The special reports listed belcw were reviewed in the Region I office to verify that the report included infomation required to be re-ported and that test results and/or supporting information discussed in the report were consistent with design predic; ions and performance specifications, as applicable.
The reports were <lso reviewed to ascertain whether planned corrective action was adequate for resolu-tion of identified problems, where applicable, and to detennine whether any inforination contained in the report should be classified as an Abnormi Occurrence.
The following TMI 2 specia'l reports were reviewed.
10 CFR 50.55(c) report, dated January 31, 1978; Reactor building ecergency cooling booster pumps did not meet system design requir r.ents.
10 CFR 50,55(e) report, dated January l!,1978; Reactor building spray pumps had a higher required NPSH than the system available NPSH during runout conditions.
Special Report 78-03, dated August 9,1978; Fire Service air intake tunnel halon system actuated during a thunderstorm and remained' inoperable for more than 14 days while the halon storage containers were being recharged and reinstalled.
The above reports were closed based on satisfactory review at the Region I office.
8.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph
- 1) at the conclusion of the inspection on September 7,1978.
The in-spector sunnarized the purpose and scope of the inspection and the F
findings.
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Reference 32 REGULATORY INFORMATION DISTRIBU'isun o v o i tre snavos DISTRIBUTION FOR INCOMING MATERIAL 50-320 D2: ORIER B H ORG: HEREEIN J G DOCDATE: 07/24/76 NRC METROPOL EDISON DATE RCVD: 08/04/ '
3CTYPE: LullEn NOTARIZED: NO COPIES RECEIVEE JBJECT:
LTR 1 ENCL 1 (ANSMITTAL OF A SPECIAL REPORT CONCERNING THE EMI-2 ECCS ACTUATION WHICH CURRED ON 4/23/78.
. ANT NAME: THREE MILE ISLAND - UNIT 2 REVIEWER INITIAL:
XRS DISTRIBUTOR INITIAL: pg toco u* ******** ** D ISTR IBUT ION OF TH IS MATERI AL IS AS FOLLOWS * *** ***** *** *+ + ++
)TES:
SEND AMENDMENTS ONLY TO WETMORE PSAR/FSAR AMDTS AND RELATED CORESPONDENCE (DIGTRIBUTION CODE B001)
ER CHIEF LWR #4 BC**LTR ONLY (QSJ,T jlIR VASSALhO*4L4F.- C4Y FOR ACTION:
PROJ MGR H.
SILVER **W/ ENC LIC ASST LWR #4 LA**LTR ONLY INTERNAL
- REG FILE **W/ ENCL NRC PDR**W/ ENCL I & E**W/2 ENCL OELD**LTR ONLY OPERATOR LIC BR**W/ ENCL EMERGENCY PLAN BR**W7 ENCL QAB**W/ ENCL DIRECTOR NRR**LTR ONLY MIPC**LTR ONLY AD FOR ENG**LTR ONLY.
MECH ENG BR**W/ ENCL STRUCTURAL ENG BR**W/ ENCL MATERIAL ENO BR**W/2 ENCL AD FOR REAC SFTY**LTR ONLY REACTOR SYSTEMS BR**W/ ENCL ANALYSIS BR**W/ ENCL CORE PERFORMANCE BR**W/ ENCL AD FOR PLANT SYSTEMS **LTR ON AUXILIARY SYS BR**W/ ENCL CONTAINMENT SYSTEMS **W/ ENCL I & C SYSTEMS BR**W/ ENCL POWER SYS BR**W/ ENCL AD FOR SITE TECH **W/5 ENCL AD FOR SITE ANLYS**LTR ONLY ACCIDENT ANALYSIS **W/ ENCL EFFLUENT TREAT SYS**W/ ENCL RAD ASSESSMENT BR**W/ ENCL KIRKWOOD**W/ ENCL GEOSCIENCES BR**W/ ENCL EXTERNAL:
LPDR'S HARRISEURG, PA**W/ ENCL TERA **W/ ENCL NSIC**W/ ENCL ACRS CAT B**W/16 ENCL o
i ISTRIBUTION:
LTR 58 ENCL 48 CONTROL NBR:
782160092 IZE: 1P+4P l
occoo*****************************
THE END
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