IR 05000298/1982007

IE Insp Rept 50-298/82-07 on 820301-0430.No Noncompliance Noted.Major Areas Inspected:Operational Safety Verification, Monthly Equipment Surveillance & Maint Observations,Review of Plant Operations,Reactor Scram Review & Independent Insp

ML20054M452
Person / Time
Site:	Cooper
Issue date:	06/14/1982
From:	Dubois D, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20054M449	List: IR 05000298/1982007 ML20054M448
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-2.K.3.15, TASK-2.K.3.22, TASK-2.K.3.24, TASK-2.K.3.25, TASK-2.K.3.28, TASK-TM 50-298-82-07, 50-298-82-7, NUDOCS 8207130251
Download: ML20054M452 (12)

Text

. .

APPENDIX U.S. NUCLEAR REGULATORY COMMISSION l

REGION IV

Report N /82-07 Docket N Licensee: Nebraska Public Power District P. O. Box 499 Columbus, Nebraska 68601 Facility Name: Cooper Nuclear Station Inspection At: Cooper Nuclear Station, Nemaha County, Nebraska tor: # N D. L. DuBois, Resident Reactor Inspector Date Reactor Project Section A Approved By: 4 T. F. Westerman, Chief M

Date

/kL Reactor Project Section A Inspection Summary _

Inspection on March 1 - April 30, 1982 (Report No. 50-298/82-07)

Areas Inspected: Routine, announced inspection of operational safety verification; monthly equipment surveillance and maintenance observations; review of plant operations; observation of annual emergency preparedness exercise; reactor scram review; independent inspection; follow up of licensee events, circulars, and TMI action plan requirements. This inspection involved 159 inspector-hours onsite by one NRC inspecto Results: Within the areas inspected no violations or deviations were identifie .

8207130251 B20623 PDR ADOCK 05000298 O PDR

,

. .

DETAILS Persons Contacted

• L. Lessor, Plant Superintendent P. Thomason, Acting Operations Supervisor L. Lawrence, Maintenance Supervisor '

J. Sayer, C & HP Supervisor C. Goebel, Administrative Supervisor V. Wolstenholm, QA Supervisor A. Brungardt, Surveillance Planner R. Peterson, Reactor Engineer L. Bednar, Electrical Engineer D. Norvell, Electrical Foreman

• Indicates presence at exit meeting . Operational Safety Verification The NRC inspector observed control room operations, instrumentation, controls, reviewed applicable logs, and conducted discussions with control room operator The inspector verified operability of:

'A' Core Spray System

'B' Core Spray System

'A' RHR System

1. 2 Diesel Generator Standby Liquid Control System Service Water Booster System The inspector reviewed safety clearance records, including verification that affected components were removed from and returned to service in a correct and approved manner, that redundant equipment was verified operable, and that limiting conditions for operation were adequately identified and maintaine The inspector also verified that maintenance requests had been initiated for equipment discovered to require repair or routine preventative upkeep, appropriate priority was assigned, and maintenance commenced in a timely manner commensurate with assigned prioritie Tours of accessible areas of the facility were conducted to observe normal security practices, plant and equipment conditions including cleanliness, radiological controls, fire suppression systems, emergency equipment, potential fire hazards, fluid leaks, excessive vibration and instrumentation adequac These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established in the Technical Speci-fication, 10 CFR, and Administrative Procedure No violations or deviations were identified in these area _. . - .

. .

3 Surveillance Observations The inspector observed portions of Technical Specification required surveillance tests to verify that testing was performed in accordance with adequate procedures, test instrumentation was in calibration, limiting conditions for operations were met, removal and subsequent restoration of affected components was accomplished, test results conformed with Technical Specification and procedure requirements, tests were reviewed by personnel other than the person directing the test, and deficiencies identified during testing were properly reviewed and resolved by appropriate management personne These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established in the Technical Speci-fication,10 CFR, and Administrative Procedure No violations or deviations were identified in these area . Maintenance Observations The inspector observed portions of the following maintenance activities:

MWR 82-0334, 'C' Fire Pump Overhaul MWR 82-0638, Radwaste Ventilation Exhaust Modification MWR 82-0657, RHR-M0-89B Valve Intervals Modification MWR 82-0788, 'D' Service Water Booster Pump Shaft Packing Replacement

• MWR - Maintenance Work Request The following Clearance Orders were independently verified for proper placement /

restoration of affected components:

82-086, 'C' Fire Pump

[

82-098, Heating Boiler Fire Sprinkler System 82-101, High Pressure Coolant Injection Pump I 82-103, High Pressure Coolant Injection Pump

'82-133, 'A' Standby Liquid Control Pump 82-134, 'B' Standby Liquid Control fump 82-136, Residual Heat Removal System Valve M0-16B 82-138, Residual Heat Removal System Valve M0-16A 82-166, 'A' Diesel Generator Fuel Oil Storage Tank'82-171, 'L' Sump Discharge To The River 82-178, Fire Protection System Cardox Storage Tank 82-202, 'B' Core Spray Pump 82-205, 'A' Residual Heat Removal Pump 82-209, 'A' & 'C' 3ervice Water Booster Pumps82-215, 'B' & 'D' Service Water Pumps82-216, 'A' Air Compressor 82-222, 'D' Service Water Booster Pump 82-226, Security Lighting 82-230, Radwaste Ventilation

. .

Included with the above were checks for availability of redundant equipment, adequate safety isolation and clearance, accomplishment of work in accordance with approved procedures and Technical Specification requirements, verification that QC checks were performed as required, cleanliness controls and health physics coverages were adequat No violations or deviations were identified in the above are . Review of Plant Operations The NRC inspector attended an emergency plan / emergency plan implementation procedures training session, which was presented by the CNS emergency coordinator on February 26, 1982. Attendees consisted of licensee personnel who are assigned responsibilities and duties during onsite and offsite emergencies. The inspector reviewed the training presentation agenda, lecture materials and aids, and attendance records, for thoroughness and adequac The inspector observed a site emergency drill which was conducted by the licensee on March 1, 1982. The inspector verified that licensee organizational response was in accordance with approved procedures and plans, that the response appeared coordinated and timely, that the drill was evaluated by appropriate licensee personnel, and that appropriate corrective actions were initiated to correct identified deficiencie No violations or deviations were identified by this inspecto . Annual Emergency preparedness Exercise The inspector acted as a control room observer during the licensee's annual emergency preparedness exercise which was conducted on March 10, 198 The scenario for this exercise developed from a series of simulated plant equipment problems and electrical system failures that' required response from onsite licensee personnel only to conditions requiring activation and response from offsite licensee, county, state, and federal agencies. Radiological emergency response plans, procedures, equipment, and emergency operations control centers were activated by all affected agencie The inspector's comments concerning the exercise are integrated into NRC Report 50-298/82-0 No violations or deviations were identified by this inspecto . Plant Scram - Safety System Challenge The inspector reviewed records and interviewed plant personnel concerning an unscheduled reactor scram, which occurred on March 20, 1982, at 8:20a.m.,

(Scram Report #82-01). The plant was at full power, normal operating conditions prior to the scram. Control room operators had been experiencing oscillations in the main generator automatic voltage regulator system and took action to place voltage control in the manual mode. Upon placing the voltage regulator

. .

to manual, generator excitation voltage rapidly decreased and before further operator action could be implemented, resulted in a generator trip, which directly caused a reactor scram due to Turbine Control Valve fast closur All other systems functioned as designed. Appropriate corrective action was taken and the facility remained shutdown until March 22, 1982, to facilitate various maintenance activities. No unreviewed safety questions were discoveru . Licensee Event,Tollowup The following LERs are closed on the basis of the inspector's inoffice review, review of licensee documentation, and discussions with licensee personnel:

LER 81-11 Core Spray Header Break Detection Instrument Sensing Lines Reversal LER 81-13 Exceeding Battery Discharge Rate During Performance of S.P. 6.3.1 LER 81-14 High Pressure Coolant Injection Pump Turbine Trip LER 81-16 Incorrect Core Thermal Power Calculation LER 81-23 Operation With Uncalibrated Temperature Switch MS-TS-148D 9. IE Circulars (Closed) Role of Shift Technical Advisors (STA) and Importance of Reporting Operational Events Cooper Nuclear Station has assigned the duties and responsibilities of the STA to the crew shift supervisor. NRC acceptance of the shift supervisors dual role is documented in a letter from Vassallo to Pilant I dated April 1, 198 The shift supervisors are responsible for all safety and nonsafety-related activities that occur in their assigned shifts. They are kept informed of normal and off-normal events that occur during their absence by adherence to normal shift turnover procedure requirement CNS Administrative Procedure 1.26, " Routing Procedures for Operati_ng Experience Review," assures that information relevant to CNS plant operations, including operating events experienced by other utilities, is available for the shift supervisorsrev:ew and consideration. Also, sufficient guidance is readily available in the control room for use by the shift supervisor in evaluating off-normal events, and to determine NRC report-ability requirements, including the method by which reportability is to be accomplishe (Closed) Inadequate Periodic Test Procedure of PWR Protection System The CNS Reactor Protective System (RPS) consists of two separate and indeoendent RPS busses designated 'A' and 'B'. Bus 'A' normally receives AC power from MG set 'A' and bus 'B' from MG set 'B'. An alternate source of power is available to supply either RPS bus should its respective MG set be removed from service. Each MG set output breaker is protected by overvoltage, undervoltage, and underfrequency devices, either of which, if activated, would trip open the affected MG set output breaker, thus isolating the affected MG set from its associated RPS bu .

.

The NRC has required the licensee to install seismic qualified trip devices in each MG set output circuit, and also to the alternate power supply source. The licensee will install the required trip devices during the Spring 1982 refueling outage in accordance with Minor Design Change (MDC)80-133. The new trip devices will include overvoltage, under-voltage, and underfrequency protection functions. Each trip device will have the capability to be independently tested and verified. A new Surveillance Procedure, S.P. 6.1.35, will be written and approved for use in testing each trip function. _CNS Technical Specification will be amended following completion and testing of the modified protection system. In a letter from Vassallo to Pilant, dated May 4, 1982, NRR has stated that the proposed design modifications, as described by the licensee, are acceptable.

10. NUREG-0737 Clarification of TMI Action Plan Requirements Item II.F.1.6 (Closed) Accident Monitoring - Containment Hydrogen NUREG-0737, Item II.F.1, Attachment 6, Containment Hydrogen Monitor, requires that continuous indication and recording of containment hydrogen concentration be available within 30 minutes of the initiation of safety injection. Also, measurement capability shall be provided over the range of 0-10% hydrogen concentration under both positive and negative ambient pressure conditions. Licensee due date for this item was January 1, 198 The NRC inspector has verified licensee actions with regard to this item based upon a letter from Pilant to Eisenhut, dated April 16, 1982, which states that this item is complete. The licensee also referenced a letter from Pilant to Eisenhut, dated June 30, 1981, which states that the containment hydrogen monitoring system analyzers have ranges of 0-5% and 0-20%, respectively. The licensee does not intend to alter the present system desig Item II.K.3.15 (Closed) Modify Break-Detection Logic to Prevent Spurious Isolation of High-Pressure Coolant Injection and Reactor Core Isolation Cooling The NRC inspector has verified licensee actions with regard to this item based upon the following:

(1) Letter from Pilant to Eisenhut, dated June 30, 1981, states that a design change was completed which eliminates spurious isolations during a normal system startu (2) Letter from Ippolito to Pilant, dated October 14, 1981, requested further information with regard to this ite (3) Letter from Pilant to Ippolito, dated November 2, 1981, provided further information as requested in (2) abov .-. - . - _ . .. . . . . - . _ .. - - ~ - -

. .

(4) Letter from Eisenhut to All Licensees of Operating Power Reactors, dated March 17, 1982, requested a reconfirmation of the completion date for this ite (5) Letter from Pilant to Eisenhut, dated April 16, 1982, reconfirmed the completion date of this item as requested in (4) abov The HPCI and RCIC pipe break-detection logic modification was completed June 1, 1981, in accordance with Minor Design Change (MDC) 81-00 Licensee completion due date for this item was January 1,198 The inspector reviewed representative samples of as-built drawings, Procedures 6.2.2.3.1 and 6.2.2.6.1, CNS Technical Specification Amendment No. 75, and MDC 81-006 to verify that:

(1) MDC 81-006 was reviewed and approved in accordance with the CNS Technical Specification and established QA/QC control (2) Design changes were controlled by established procedure (3) Postmodification testing was accomplished, reviewed, and found acceptable by the license (4) Procedures and as-built drawings were revised to reflect the modificatio (5) Applicable licensee personnel received training commensurate with the modificatio The insoector's review of the installed equipment and related documentation verified that the modification was in conformance with the requirements of NUREG-0717, Item II.K.3.15, and Task- Item II.K.3 of TI 2515/5 c. Item II.K.3.22 B (closed) Reactor Core Isolation Cooling Suction -

Modification The NRC inspector has verified licensee actions with regard to this item based upon the following:

(1) Letter from Pilant to Eisenhut, dated December 30, 1980, the licensee gave a committment'date for addressing or completing this TMI action item, (2) ' Order' from Ippolito to Pilant, dated July 10, 1981, the order acknowledged the committment given in (1) abov (3) Letter from Ippolito to Pflant, dated September 1, 1981,-the NRC stated that the licensee's proposed plant modification applicable to this TMI action item was to be considered unresolved and would be the subject of future correspondenc . .

(4) Letter from Pilant to Eisenhut, dated December 28, 1981, the licensee stated that this TMI action item was complete (5) Letter from Eisenhut to All Licensees of Operating Power Reactors, dated March 17, 1982, the NRC requested reconfirmation of the licensee completion date for this TMI action ite (6) Letter from Pilant to Eisenhut, dated April 16, 1982, the licensee resubmitted to the NRC their completion date for this item as requested in (5) abov The RCIC suction modification was completed November 5, 1981, in accordance with Minor Design Change (MDC)81-098. Licensee completion due date for this item was January 1, 198 The inspector reviewed representative samples of as-built drawings; Procedures 2.2.67, 2.3.2.22, 6.2.2.3.4, 6.3.6.2; and MDC 81-098 to verify that:

(1) MDC 81-098 was reviewed and approved in accordance with the CNS Technical Specification and established QA/QC control (2) Design changes were controlled by established procedure (3) Postmodification testing was accomplished, reviewed, and found acceptable by the license (4) Procedures and as-built drawings were revised to reflect the modificatio (5) Applicable licensee personnel received training commensurate with the modification.

The inspector's review of the installed equipment and related documentation verified that the modification was'in conformance with the requirements of NUREG-0737, Item II.K.3.22b and Task Item II.K.3 of TI 2515/5 d. Item II.K.3.24 (Closed) Confirm Adequacy of Space Cooling for High Pressure Coolant Injection and Reactor Core Isolation Cooling Systems The NRC inspector reviewed the following documentation with regard to this item:

(1) Letter from Pilant to Eisenhut, dat(d June 30, 1981, stated that HPCI and RCIC room coolers receive power from emergency busses so they would be unaffected by loss of offsite powe (2) Letter from Eisenhut to All Licensees of Operating Power Reactors, dated March 17, 1982, the NRC requested that the licensee confirm the adequacy of HPCI and RCIC space cooling during a loss of off-site powe (3) Letter from Pilant to Eisenhut, dated April 16, 1982, the licensee reconfirmed the completion and adequacy of the room coolers as requested in (2) abov ,__

. .

The inspector's review of the above correspondence, related plant documents, and installed equipment has provided assurance that the licensee appears to be in conformance with the requirements of NUREG-0737, Item II.K.3.24, and Task Item II.K.3.24 of TI 2515/5 Licensee completion due date for this item was January 1, 198 Item II.K.3.25.B.1 (Closed) Power on Pump Seals - Modification i

The NRC inspector has verified li.censee actions with regard to adequate recirculation pump seal design during loss of offsite power based upon the following:

(1) Letter from BWR Owners Group to NRR, dated May 22, 1981, submittal of the BWR Owners Group evaluation of pump seal degradation caused by a complete loss of seal coolin (2) Letter from Pilant to Eisenhut, dated June 30, 1981, states licensee concurrence with the conclusions of the evaluation submitted by the BWR Owners Group in (1) abov (3) Letter from BWR Owners Group to NRR, dated September 21, 1981, submitted supplemental information to NRR concerning pump seal degradation during a complete loss of seal coolin (4) Letter from Eisenhut to All Licensees of Operating Power Reactors, dated March 17, 1982, states that licensee replies to this item have been received and are under revie Recirculation pump seals are normally supplied cooling water from two systems; e.g., Reactor Equipment Cooling System (REC) and the Control Rod Drive Hydraulic System. Either cooling system can be supplied power from the emergency electrical-power system. The licensee has stated that if both cooling systems become inoperable simultaneously, recirculation pump seals would begin to deteriorate after approximately 7 minutes, but would not lead to excessive loss or reactor coolant to become a safety concer The inspector has determined that licensee committments appear to conform to the requirements of NUREG-0737,; Item II.K.3.25.B, and Task Item II.K.3.2 of TI 2515/59. Licensee completion due date for this item was January 1, 198 f. Item II.K.3.28 (Closed) Qualification of ADS Accumulators NUREG-0737, Item II.K.3.28 states, " Safety analysis reports claim that air or nitrogen accumulators for the automatic depressurization system (ADS) valves are provided with sufficient capacity to cycle the valves open five times at design pressures. GE has also stated that the emergency core cooling (ECC) systems are designed to withstand a hos+,ile environment and still perform their function for 100 days following an acciden Licensee should verify'that the accumulators .on the ADS valves meet these requirements, even considering normal leakage. If this cannot be demon-strated, the licensee must show that the accumulator design is still acceptable."

. .

The NRC inspector has verified licensee actions with regard to this item based upon the licensee's review and evaluation of the Automatic Depressurization System (ADS) capabilitie The inspector has reviewed the following documents related to this item:

(1) IE Bulletin 81-01, Operability of ADS Valve Pneumatic Supply

(2) Letter from Pilant to Seyfrit, dated January 16, 1980, licensee response to IE Bulletin 80-01 (3) IE Inspection Report No. 50-298/80-09, dated July 14, 1980, paragraph 6, IE inspection follow up to IE Bulletin 80-01 (4) Letter from Pilant to Eisenhut, dated December 12, 1981, which states that the licensee completed the review and evaluation of the ADS

>

accumulator qualifications and has verified that the accumulators meet FSAR design requirement (5) Letter from Eisenhut to All Licensees of Operating Power Reactors, dated March 17, 1982, states'that the licensee's submittal, Item (4)

above, is presently under revie Licensee completion due:date for this item was January 1,198 . Exit Meetings Exit meetings were conducted at the conclusion of each portion of the inspection.

The Plant Superintendent was informed of the above findings.

I

..e.w, r., . . . -,-

Page 1 of 2  ;

I Nac FORM 798 U.S. NUCLEAR REGULATORY COMMISSION PRWCIPALINSPECTom(Name. ust wst. anarence area m en

"

INSPECTOR'S REPORT DuBois. Dennis REVIEWER Office of Inspection and Enforcement Westerman. Thomas WSPECTO45 D. L. DuBois UCENSEE/vtNDOR TRAN A CN REPO47 NEXT INSPEC. DATE p 00CKET NO (8 dets)OR UCENSE NO.(BY PRODUCTHt3dets' N S E M YR Nebr. Public Power District ~

X

'~**'"'

0 5 0 0 0 2 9 8 81 2 0 7 a F. U. box 499 u - MM*Y a Columbus, Neb b6601 ] O - onETE Cl R - REPLACE D

.<% *MyMt* N#W 0; "3C; * " ~'

.i ~ 14 15 18 F E CO OF INVESTIGATION / INSPECTION WSPECTION PERFORMED BY CAGANIZATCN COCE OF REGCNIHQ CONDUCT-FAOM TO 1 - REGCNAL OFFICE STAFF lOTHER 'N #'

y m-weeerv Mar cower R earvem * kw coce y M DAY V M OAY YR y 2 - RESIOENT INSPECTOR AEGON ,

DivlS60N a BRANQM 013 0 11 R I? n la 310 Al ? 3 - "a 'o""^*c' ^a ^'$^' *" 4 l C I A m e r: w :3e m.; w m a nwsew&cznws:w n , 3s t 34 l 25 REGONAL ACTION TYPE OF ACTIVITY CONDUCTED ' Check one con onivi X 02 - SAFETY _

06 - MGMT. VISlf _

10 - PLANT SE INQUIRY

_

1 - NIC FORM 581 03 - INCIOENT 07 - SPECIAL 11 - INVENT. VE t.4VESTIGATION X 2 - KEGCNAL OFFICE LETTER 04 - ENFORCEMENT 08 - VENDOR 12 - SHePMENT/ EXPORT 05 - MGMT. AUDs7 09 - MAT. ACC .lM POR T

, ' n* T % '%MWB " sW y& p; % C %%7:Q.g % r*?f}J Q r*'N 2.;~.%y's"Y e 31 3 - ,

eN5PEGT4NaNvE5 6* GAT 4N ANONG5

>Chece oae w w TOTAL NUMBER ENFORCEMENT CONFERENCE REPOR T CONTAIN 2130 LETTER OP REPO4T TR ANSMITTAL DATE OF VCLATONS ANO HELO INFOR M A TION A 8 C D CEviATONS NRC FORPA 591 RE80RT SENT

_

OR RE*). TO HO. FOR LETTER IS 30E0 ACTION 2 - VCtATCN 3 - CEVIATCN A l 8 lC 0 Al8lC 0 Al8 C D M DAY lYR MO OAY l YR 4 - vCLATION & OEVIATON , l , l , l l 1 - YES l 1 VES Db M38kjl l l l

? h%$YN?$5.YY kN- ',&bb l ' b'? $ " "#

MODULE INFORM ATION MODUL E INFORM ATiON MODULE NUM8ER INS yg g MODULE REQ. FOLLOWUP d MODULE NUM8Em iNSP yg a 900VLE RECL FOLLOWUP U

5 - #5 -

r 8 5

..

- $8h3 3o hfac$5: a

= . 55 r

8 . s r

65 . c Q3 h!$c ie E E <: . !!

r r 2 4

2 I 8 2 %o u--2 y. 2 o

, . 2

< 83

.

ye . <2 . u--2 _m .$5 .

i E i5 : ! : y!sr$s s

t r8e

<

<

E s$5 . 23 : :

s

<

I

<

s$ 5, 3 y2 h * 2t

* E 1!sa$d E 3r82 5i a c 5 y

= v o 2 fi y

'

8 , 5 2,5 l5,4,3 lB ^

0,0,4 Oi 8,5 , lr , le , 5 6 si l7 :2 i6 l

^

O i0 id l ic io C i liil

~

r , , , , li i l '

i i i i i liil c

i i , i i lt -

l C i i i i i Iiil c , , , , i liil , i i i , IiiI

'

8 i 5 2i Sl 5,5,2l ^ 0,0 i 8 0,7,5 , l,,le i 5 6,2l7,0,3l ^

Oi0i6 li0i0 C i lt i i

• li,l *

, , , i i r i e i i liiI c

i , i , , I,,1 e i i i i , liil

, , , , , l,,I c , , , , , I1 i l 1* i 5 2,5l 5,5,9l B ^ 0,1,8 0,7,3 , li,l . , 5 7,1l7,0 7 i l

^ 0,2 i6 0,8,1 C , l,,l

j I i t i i i , l '

I i i l ll[l!

I t i f f i , , i f i f Iit I l i , , , , li,I i i i i i l, i l i 1 5l 3,0l 7, 0,3l ^

Oi 2, 4 , , i l,il . i 5 7,1l7,0,9 l ^

O24O88C i i i I

i liil t i f f , , , i l i 1 i ll t l l 1 I i , i f I i i f I l !

O C:RCtf SEQUENCE IF I O i I D C 8 i

VIOLATION OR DEvlATION , , ,, i l , , l l l , i 7 l [ l , j

'Ji l 1, , , __ L1___1 2 _-

,

Page 2 of 2 NacFORu7es U.S. NUCLEAR REGULATORY COMMISSION PRINCIML INSPECTOR (Nw tst. Arst. aennee artes d 11 -811

• E MC OL16 INSPECTOR'S REPORT ,,y,,,,

Office of Inspection and Enforcement

.NSPECTOIS LICENSEE /vtNDOR TRANSA TCN "I 00CKET NO i8 d9tsa OR LICENSE NO.<8Y PRODUCT 1113d9tse N S E M Y "'"'

_ 0 5 0 0 0 2 9 8 ^

M - M00lFY es

-

0 - DELETE C

-

R - REPLACE D

+ -ef~;2,Q%r(.kM ' 3*:f%< T '& > n

.

L.? J > 14 15 - 18 PE-CO OF INVE S TIGATION/INSPECTON IN$PECTION PERFORMED BY ' ORGANIZATION CODE OF REGCN/HQ CONOUCT-FROM TO 1 REGIONALOFFICESTAFF OTHER eg-hees4 Marvower Rscorreg . kw coce y M DAY l Y M DAY Y RES10ENTINSPECTOR A EGCN ! OdV'SCN BRANCM l 3 - PERFORMANCE APPRAISAL TEAM l l l l l l f 3 . D +i ? W3f Ng /.Y W $Ol y3k f?y QMW) J w siL/] Cy*c.,#,('4 Q'2? .M W'

~

_

,

_'. , 33 . l 34 f 35 REGIONAL ACTION TYPE OF ACTivlTY CONQUCTED (Cheet one nos orwve

"*

02 - SAFETY _

06 - MGMT. VISIT 10 - PLANT SE INQUIRY 1 - NAC FORM $01 03 - INC10ENT 07 - SPEC lAL 11 - INVENT.vE INVESTIGATON 2 - REGCN AL OFFICE LETTER 04 - ENFORCEMENT 08 - VENDOR 12 - SHIPMENT /EXPOAT 05 - MGMT. AUDIT 09 - MAT. ACC NPORT y NV,Vfgp5 M4F%f*f$n' Wir '%fW" 3 W "N.*fM ?'. 'T9EM N

.NsFE G T.ON oN y t 5 i.GA T*Q N F'NQiN GS

'c * " "' # TOTAL NUMBER ENFORCEMEN T CONFERENCE REPOR T CON TAIN 2390 LET'ER CP REPOAT TR ANSMITTAL 0 ATE OFVCLATCNS At40 MELO INFORMATION A 9 C 0 CEviATONS NRC FORM 591 REPORT SENT 1 - CLEAR OR Rg TONO.FOR LETTER tS30E0 ACTION 2 - VIOLATION 3 - OEvlATION A 0 0 B C Al8fC A B C 0 MO. l OAY YR M DAY YR 4 - VOLATION & DEvlATION , , , 1 YES 1 - YES

, l l l l l l l l l c"$-[ M[M+%$t/M Q2 6i t hh k *J 'i 4{ s . ~ 43- ' 44 49 50 ' $5 MODULE INFOR M A TION MODUL E 'NscRM AttoN kE

-

MODULE NUM8ER INS g 9 MODULE REO. FOLLOWUP h[f MODULE NUMBER INSP cg WODULE REO. FOLLOWUP e - - - r - o o -

= g5 k=  : ;!$

!gna

'

= #$ $5 5 #$ b5 e.Ebgsg i$gG !$2 $- i5 5 r

:

si  ; si ses s!= sis *fama sish E!!

s na sese i =a s!>

5 i 5 !s

! 2 15 s!i  : g 5!sss  :; I =5 s sc s I =5 : E tv - a c ' "

si si= s

. i 5 7 :1 l7 ,1,3 l ^

0,1,0 0,4,8 C , li,le i 5 9i2l7,li7l ^

00i7 i i i liil

' *

i i i i i li i l i i i i i liil c

i

, , , , , liil c i i i i i Ie i l o

, , , , i liil o

, , , i i Iiil

. , 5 8,2l7,1,2l A 0,0,8 1,0,0 C , l,, , 5 9,3l7,0,2l ^

nior2 i i i liil

i i , , , i liiI *

i i i i i liil I c

, , , , , Ii,I c i i i i i liiI i , , , , l,,I o , , , , i li,l e i 5 9:2l7,00lC^ 0,1 4 , , i li,l e i iliil ^-

i i i i i liil I{ l I

' 8 i 1 e i i i i l i l i i f i f f , , i , i l i i l i !

o i , , , i liil o

, i i i i I,ii e i 5 9,2 l7,0,6 l ^

0i0,4 , i i liil e i iliil^ i i i i l 1 liil i 1 , f , l , I f i l 1 l l i, , , f , i i i i f i l i 0 C:RCLE SEQUENCE sp I D l VIOLATON OR DEVIAT:ON l , l l l l ) l [

l l l { l l l [