ML20138A576

Annual Summary of Safety Evaluations,850311-1231

ML20138A576
Person / Time
Site:	Wolf Creek
Issue date:	12/31/1985
From:	Koester G KANSAS GAS & ELECTRIC CO.
To:	Martin R NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
KMLNRC-86-040, KMLNRC-86-40, NUDOCS 8603140321
Download: ML20138A576 (23)

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10LF CREEK GENERATING STATION DOCKET NO: 50-482 FACILITY OPERATING LICENSE: NPF-42 AlelGAL SG9ERY OF SAFETY EVAWATIGGS REIORP NO: 1 REPORP PERIOD: MARCH 11, 1985 to DECENBER 31, 1985 Sutmitted by:

Kansas Gas & Electric Company l

O 8603140321 851231 i PDR ADOCK 05000482 R PDR

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' Annual Stunary of Safety Evaluations l

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tis report contains a sunnary of safety evaluations on pcc+csed changes, tests and experiments performed pursuant to 10 CFR 50.59(a), between March l 11,'1985 '(receipt of facility operating license) and. December 31, 1985.

l Wis report is being subnitted in accordance with the requirenents of 10 CPR 50.59 (b) .

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1. - Plant- 2dification Request (PMR) #00311 - Originated to facilitate the

! redesign of the Service Air systen air compressors to reduce dirt l . intake and control cooling water flow. No unreviewed safety or l environmental questions are generated as a result of this change.

.,. 2. Plant edification. Request #00450 - Replacement of screen in the containment spray suction recirculation sump enclosure. No unreviewed safety or environmental questions are generated as a result of this change.

3. ' Plant Modification Request #00465 - Replacanent of existing neutron

' shield water bags with stainless. steel cans. No unreviewed safety or environmental questions are generated as a result of this change.

4. Plant Modification Request #00555 - Modification of the drains of the neutron shield water bags. No unreviewed safety or environmental questions are generated as a result of this change.

5. Plant' Modification Request #00565 - Rewired annunciators to put close contacts in series .in the Solid Radwaste System Alarn panel HC 145.

No unreviewed safety or environmental questions are generated as a result of this change.

6. Plant mdification Request #00567 - Revision of drawings to reflect the "as built" installation location of receptacles in the cold

, chenistry laboratory. No unreviewed safety or envirorunental questions j are generated as a result of this change.

7. Plant Modification Request #00577 - Addition of a liquid drain tap in the suction line and a recirculation line to the waste gas i

ccupressors. No unreviewed safety or envirorinental questions are i generated as a result of this change.

'8. Plant Modification Request #00577, Revision 3 - W e original PMR and Revisions 1 and 2, as repo ted in Mar &,1985, doctanent the addition of a recirculation line with a pressure regulated control valve and ,

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the addition of a liquid drain trap on the suction line to each Waste Gas Canpressor, SHA02A and B, to prevent loss of units with inadvertent closed discharge. Revision 3 provides engineering

. disposition to certify conformance of purchased and installed valves with Regulatory Guide 1.143, Table 1 requirenents of D-Augmented Special Scope. lines. No unreviewed safety or environmental questions  !

are generated as a result of this modification.

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, 9. Pla6t Madification Request #00583 - Rework of Ruskin fire danpers due to failure of the dampers to cloae'if flow is present in the ductwork. No unreviewed safety or enviromental questions are generated as a result of this change.

10. Plant M3dification Request #00591 - Addition of R-C networks and

- varistors to the sanple and reager.t. station of the Solid Ra3 waste System. No unreviewed safety or e.wironmental questions are generated as a result of this change.

11. Plant H3dification Request #00606 - Addition of overcurrent protection in contaiment electrical penetrations. No unreviewed safety or environmental questions are generated as a result of this change.

12. Plant Modification Request #00606 (Revised) - Upgrade of fusing protection at contairunent electrical penetrations. 'Ihe PMR was evaluated and it was determined that no unreviewed safety or err'ironmental questions are generated by this change provided the mooification was empleted prior to Mode 4 operation.

13. Plant Modification Request #00615 - Implement wiring enange for handswitch SB HS-1, Manual Reactor Trip Breaker Control to improve breaker reclosure reliability following a trip operation. No unreviewed safety or envirorrnental questions are generated as a result of this change.

14. Plant H)dification Request #00637 - Addition of a closure to a fire penetration t.hrough a seismic block wall in the Auxiliary Building.

No unreviewed safety or environmental questions are generated as a result of this charge.

15. Plant Modification Request #00646 - Relocation of radioactive waste compactor from the Containment Buildiry to the Radwaste Building. Na unreviewed safety or environnental questions are generated as a result of this change.

16. Plant M3dification Request. #00654 - Seal floor penetrations in Spent Rosin Sluice Ptung Boon of the Radwaste Building to prevent possible spread of contanination in accordance with ALARA program. No unreviewed safety or environnental questions are generated as a result of this change.

17. Plant Modification Request #00601 - Rework of a leaking check valve, AE-V-121, in the Main Feedwater System. The PMR was evaluated, and it was determined that no unreviewed safety or environmental questions are generated as a result of this charge.

18. Plant Hadification Request #00726 - Replacement of the Stean Generator Pipe Peak Recording Acceleraneter (SGAR7) with one of a higher range.

No unreviewed safety or envirormental questions are generated as a result of this change.

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19. ' Plant Madification Request #00743 - Change the storage location of the l reactor vessel 0-rings to the top of the pressurizer enclosure ard

- change the storage location of the reactor cavity seal ring lifting fixture to the bottm of the fuel pool. No unreviewed safety or enviromental questions are generated as a result of this change.

20. Plant Modification Request #00798 - Replacement of instrm ent ,

air / backup nitrogen systs brass tee with a type 316 stainless tee on I a valve in the Auxiliary Feedwater System. No unreviewed safety or envirormental questions are generated as a result of this change.

21. Plant Modification Request #00808 - Modify the Power Operated Relief Valves, BB-PCV 455A and 456A, to increase the clearances between the plugs and cages of the valves. 'Ihe PMR was evaluated, and it was determined that no unreviewed safety or enviromental questions are generated as a result of this change, provided the modification was empleted prior to mde 3 operation.

22. Plant Modification Request #00816 - Addition of seal table drains to prevent drainage onto the thimble guide tubing. No unreviewed safety or enviromental questions are generated as a result of this change.

23. Plant Modification Request #00823 - Change cable termination points to support reactor trip signal P-4 interlock logic. The PMR was evaluated and it was determined that no unreviewed safety or environmental questions are generated as a result of this change, provided the modification is empleted prior to Mode 2 operation.

24. Plant Modification Request #00849 - Originated to provide permanent connections for demineralized water, compressed air, power and other services for a portable radwaste solidification processing skid. No unreviewed safety or envirormental questions are generated as a result of this change.

25. Plant M3dification Request #00852 - Relocation of the bellows seals on level transmitters in the Boron Recycle and Liquid Radwaste Systems for ALARA considerations during calibration. No unreviewed safety or enviromental questions are generated as a resalt of this change.

26. Plant m dification Request #00882 - Originated to delete a flow switch frm the plant heating system. Flow switch causes frmluent false trips of the' hot water peps. No unreviewed safety or environmental questions are generated as a result of this change.

27. Plant mdification Request 600911 - Originated to reove flush connections on Stean Generator drain pmpo and lengthen drain connection piping for increased maintainability. No unreviewed safety or environmental questions are generated as a result of this change.

28. Plant Modification Request #00920 - Originated to allow use of the )

plant O3 and N, supply rather than 0, and N3 bottles in the hydrogen i reembiner analyzer roms in accordance with ALARA program. No l unreviewed safety or environmental questions are generated as a result of this change.

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, 29. ' Plant mdification Reques't #00928 - Originated to change the alarm setpoint for the hydrogen recmbiner. No unreviemi safety or

- environmental questions are generated as a result of this change.

30. Plant Modification Request #00944 - Originated to provide a liquid drain trap at each catalytic hydrogen recmbiner purge line to prevent water from entering the gas analyzer racks. No unreviewed safety or enviromental questions are generated as a result of this change.

31. Plant Modification Request #01149, Revision 0 - Originated to allow the installation of larger capacity hydraulic fluid reservoirs on the Main Steamline Isolation Valves, AB-HVil,14,17, arxl 20 and on the Main Feedwater Isolation Valves, AE-HV39, 40, 41 and 42, actuators to stop hydraulic fluid leakage during periodic maintenance. Wis plant modificatiun also added local pressure gauges on the hydraulic fluid lines to simplify maintenance. No unreviewed safety or enviromental questions are generated as a result of this modification.

32. Plant Modification Request #01185, Revision 2 - Originated to allow the addition of fire wrap thermo/ lag material on cables to eliminate IEEE 384-1974 separation violations between conduits (4J1106, IU3A2C, 4U3E7N,1U1119 and lJ3A) and the exposed cables on radiation monitors (GT Rr22, GT Rr31, Gr Rr32 and Gr RT41) . No unreviewed safety or environmental questions are generated as a result of this modification.

33. Plant mdification Request #01186, Revision 2 - In order to hnprove the charging procedure efficiency of the Main Stean Isolation Valves and Feed Water Isolation Valves Nitrogen Precharge System, a nitrogen bottle rack with manifold, piping, valving and local pressure indication was added. We revision docmented the FSAR change request. No unreviewed safety or environmental questions are generated as a result of this modification.

34. Plant Modification Request #01187, Revision 2 - Wis modification was originated to add isolation valves AE-V361 and AE-V362 for the purpose of isolating thermal relief valves AE-V978 anS AE-V979 fran feedwater high pressure heaters E'203A and EAE038. %e revision clarified retesting requirements and docmented an FSAR change request. Wis modification is made to facilitate maintenance activities consistent with personnel safety practices without taking both feedwater high pressure heater trains out of service simultaneously. No unreviewed safety or enviromental questions are generated m a result of this modification.

35. Plant Modification Request #01195 - Originated to route concentrated sulfuric acid addition piping direct to the high Total. Dissolved Solids Collector Tanks (WF01A&B) through Alloy 20 piping and omponents. Wis change mitigates extensive Secondary Waste Systen corrasion danage to 316L S.S. conponents and piping. No unreviewed safety or enviromental questions are generated as a result of this change.

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36. Plant M'xlification Request #01195, Revision 5 - This Plant Modification Request was originated to route concentrated sulfuric

- acid piping directly to the High Total Dissolved Solids Collector Tanks ('mmlA&B) through Alloy 20 piping and components to mitigate extensive Secondary Waste System corrosion dauage to 316L S.S. piping and cmponents. Revision 5 corrects the valve wiring and schematic diagrams for the piping changes described in the previous revision.

No unreviewed safety or environmental questions were generated as a result of this change.

37. Plant Pbdification Request 501307 - Originated in response to the identification of electrical segaatim violations in the Reactor Building. Due to practical limitations of the sp2cific raceway configurations, exposed non-class lE cables which exit Terminal Boxes TB25101 and TB 25102 and various class lE raceway and electrical equipnent in the innediate area do not meet separation criteria. We failure analysis on the subject circuits concluded that the installation.is acceptable to use-as-is. Were exists no unreviewed safety or environmental questions in the present configuration.

38. Plant Modification Request #01310 - his modification adds an emergency light inside the Contaiment Personnel Access Hatch. No unreviewed safety or enviromental questions are generated as a result of this change.

39. Plant Modification Request #01333 - In order to facilitate total draindown of the dip tanks (SHD01A, B and SHD02A, B) and the turbulator (SHD03), in the Decontamination Systen, check valves in th(

drain lines were removed, vent valves were added and vent piping was altered. No unreviewed safety or enviromental questions were generated as a result of this change.

40. Plant Modification Request #01333, Revision 2 - his Plant Modification Request was originated to add vent valves, alter; vont piping, and remove drain line check valves in the Decontanination System to facilitate total drain down of the dip tanks (SHD01A,B and SHD02A,B) and the turbulator (SHD03) . Revision 2 establishes correct naterial <xanpatibility for changes requested and described in previous revisions. No unreviewed safety or envirorrnental questions were generated as a result of this change.

41. Plant Modification Request #01389 - Wis modification established a leakage retest and visual examination of ductwork and components in the Contalment Mini Purge Systen which may have been overpressurized while initiating contaiment mini purge with an allowable high contalment pressure (35" H30) . his modification generateF Ao unreviewed safety or envirofimental questions.

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.42. . ' Plant Modification Request #01407 - This modification was. originated to install quick disconnect fittings to the end of the personnel

- access hatch door seal test connections in lieu of pipe caps. With frequent surveillance testing of the door seal, this modification reduces the possibility of danage to the test connections. No unreviewed safety or environnental questions are generated as a result of this modification.

43. Plant Modification Request #01408 - his modification was originated to correct the Piping and Instrunentation Diagran of the Feedwater Systen to reflect the correct location of the readout of a pressure indicator in the Control Boan. No unreviewed safety or environnental questions are generated as a result of this modification.

44. Plant Modification Request #01426, Revision 0 - Originated to change the valve identification ntaber on the valve associated with the Auxiliary / Fuel Building Normal Fan Exhaust Filter Adsorber Unit (FGIO2) fran IGIr-V-750 to 1GL-V-760 to eliminate duplication of valve identification numbers. No unreviewed safety or environnental ,

questions are generated as a result of this modification.

45.- Plant Modification Request 101440, Revision 0 - Originated to allow the addition of flanged connections upstrean and downstrean of Gaseous Ra! waste System drain traps, FHA 04 and FHA 05 to simplify niaintenance on the traps. No unreviewed safety or environmental questions are generated as a result of this modification.

46. Plant Modification Request #01443, Revision 0 - Originated to allow the addition of two manual valved drains to each actuator hydraulic reservoir drip pan on the Main Steanline Isolation Valves and the Main Feedwater Isolation Valves to prevent insulation contanination. No unreviewed safety or environmental questions are generated as a result of this modification.

47. Plant Pbdification Request 901445, Revision 0 - Originated to allow the inatallation of threaded pipe caps as per design on the outlet of valves AQ-V832, V879, V680, V312, V914, V920, V943, V968,' V970 and V991, of the Condensate and Feedwater Chenistry Control Systen. Wis Plant Modification also removed indication of a flow path fran the discharge of valves AQ-V879, V920, V943, V970 and V991 to the oily waste systen from the design drawirgs, as the oily waste system is incapable of handling / processing.the chemicals discharged throtrJh these valves. No unreviewed safety or envirorrnental questions are generated as a result of this modification.

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48. Plant !bdification Request #01446, Revision 0 - Originated to re-install flow elements EM-FE924, 925, 926, and 927, which are currently

- installed backwards. W ese elements are used to balance flow in the safety injection systen boron injection lines to the Reactor Coolant Systen cold legs. %e use of reverse-installed flow element differential pressure (a P) readings for balancing purposes is acceptable as P measurements between the parallel lines are canpared on a relative (in H O) basis rather than on an absolute (gpn) hasis.

Absolute flow (ggn)2is measured as total flow on another flow element, EM-FE917A or B. % is modification indicates that the flow elements will be re-installed correctly prior to any future flow balance testing or daring the next refueling outage. No unreviewed safety or i enviromental questions are generated as a result of this modification.

49. Plant !bdification Request 9KN84-076 - Installation of check valves l downstrean of Centrifugal Charging Punp Discharge Icolation Valves.

No unreviewed safety or enviromental questions are generated as a result of this change. I

50. Plant Ibdification IMquest pKN84-094 - Installation of two non-safety related isolation valves downstreau of each waste gas aanpressor to facilita % maintenance and ALARA concerns. No unreviewed safety or environmental questions are generated as a result of this change.

51. Plant Modification Request #WO82-KC015 - Installation of pipe unions in the wet pipe sprinkler system trim piping in the Fire Protection System to accannodate maintenance activities. No unreviewed safety or environmental questions are generated as a result of this change.

52. Safety Evaluation 85-SE Allow the use of a revision of the tenperature versus pressure graph for the Main Steanline Isolation Valve and Feedwater Isolation Valve accunulator precharge to keep <

valves out of low pressure alaan. No unreviewed safety or enviromental questions are generated as a result of this temporary charge.

53. Safety Evaluation 85-SE Install replacanent snubbers on KJ-PDSH-10, FJ-PDSH-ll, and KJ-PSL-12. No unreviewed safety or enviromental questions are generated as a result of this tanporary change.

54. Safety Evaluation 85-SE Install temporary pressure gauges to ,

measure Stean Generator pressure for testing purposes. No unreviewed '

safety or environmental questions are generated as a result of this temporary change.

55. Safety Evaluation 85-SE Install tanporary differential pressure gauges to measure feedwater flow differential pressure for testirg purposes. No unreviewed safety or enviromental questions are generated as a result of this tanporary change.

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56. Safety Evaluation 85-SE Install replacenent snubbers on KJ-PDSH-110, IG-PDSH-lll, and KJ-PSL-ll2. No unreviewed safety or

- enviromental questions are generated as a result of this tenporary change.

57. Safety Evaluation 85-SE-ll - Connect tenporary scaler / timer to nuclear instrunent channe] N32 for testing purposes. No unreviewed safety or environnental questions are generated as a result of this tenporary change.

58. Safety Evaluation 85-SE Temporary installation of ladders on 2047' level of Auxiliary Buildig, for testing purposes. No unreviewed safety or environmental questions are generated as a result of this tenporary change.

59. Safety Evaluation 85-SE Install tenporary bottle rack and .

nitrogen manifold at 2000' level of Turbine Building at KH-V130. No unreviewed safety or enviromental questions are generated as a result of this temporary change.

60. Safety Evaluation 85-SE Install scaffolding on Auxiliary Building roof frm Containment Air Purification ard Cleanup plenum to radiation monitor. No unreviewed safety or environnental questions are generated as a result of this tenporary change.

61. Safety Evaluation 85-SE Install scaffolding at 2020' level in Auxiliary Building for rework of danpers. No unreviewed safety or enviromental questions are generated as a result of this tenporary chage.

62. Safety Evaluation 85-SE Install saffoldig at 2010' level in Auxiliary Building for danper rework. No unreviewed safety or environnental questions are generated as a result of this temporary change.

63. Safety Evaluation 85-SE Install scaffolding at 2026' level in Auxiliary Building to facilitate electrical coMuit work. No unreviewed safety or envirorrnental questions are generated as a result of this tenporary change.

64. Safety Evaluation 85-SE Install scaffolding around Main Steanline Isolation valves for installation of insulation. No unreviewed safety or environmental questions are generated as a result of this tenporary change.

65. Safety Evaluation 85-SS Install union connections to facilitate disassenbly of the drain gas traps, FHA 02 ard FHA 03, cmim off the waste gas canpressors and off the catalytic hydrogen recmbiners. No unreviewed safety or environmental questions are generated as a result of this temporary change.

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66. Safety Evaluation 85-SE Install a manual isolation valve upstrean of a check valve in the Gaseous Ra3 waste System to allow discharge of

- gas decay tanks while maintaining nitrogen supply to the gas analyzer racks. No unreviewed safety or environmental questions are generated as a result of this temporary change.

67. Safety Evaluation 85-SE Install scaffolding on the Essential Service Water house on the 2013' elevation. No unreviewed safety or enviromental questions are generated as a result of this tmporary change.

68. Safety Evaluation 85-SE Install scaffolding around recycle evaporator skid SHE02 on 2000' elevation of LMwante buildin). No unreviewed safety or environmental questions aA generated as a result of this temporary change.

69. Safety Evaluation 85-FE Tm tall mechanical jumpers in place of solenoid valves AB-WO387 ad AB-WO44C which pennit operation of stean dmp valves AB-WO38 and AB-WO44 until the solenoid valves can be icplaced. % is change does constitute a change to the PSAR, however no unreviewed safety or environmental questions are generated as a result of this tmporary change.

70. Safety Evaluation 85-SE Change the " Hot StaMby to Cold Shutdown" procedure, Gm 00-006, Rev. 6, step 4.13 to manually isolate steau dung valves AB-WO38 and AB-WO44 until solenoid valves AB-WO38B and AB-WO44C are replaced. Wis permits "as-designed" operation. No unreviewed safety or enviromental questions are generated as a result of this tmporary change.

71. Safety Evaluation 85-SE Install pressure instrunentation at existing pressure points to monitor feedwater heater performance.

Instrumentation added downstrean of existing isolation valves. No unreviewed safety or envircrrnental questions are generated as a result of this tmparary change.

72. Safety Evaluation 85-SE Change the " Power Operation" procedure, Gm 00-004, Rev. 2, to limit reactor power to < 30% until solenoid valves AB-WO38B and AB-WO44C are replaced on""steau danp valves AB-WO38 and AB-WO44. Wis permits rejection of all load without a reactor trip. No unreviewed safety or environmental questions are generated as a result of this tmporary change.

73. Safety Evaluation 85-SE Install scaffolding in the Access Control Area of the Radiological Control Area. No unreviewed safety or environnental questions are generated as a result of this temporary change.

74. Safety Evaluation 85-SE Install scaffoldina in Auxiliary Building area 5. Due to close proximity of Main Stean'.ine Isolation Valves' actuators and main stean safety valves and potential for danage to sane in event of scaffolding collapse, restricted installation to Modes 4, 5, and 6. No unreviewed safety or environmental questions are generated as a result of this temporary change.

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75, Safety Evaluation 85-SE Change in procedure STS-IC-925, "Contairrnent Coolers Flow Rate Verification", to allow use of

- essential service water pumps rather than normal service water, allow l collection of additional data and provide a caution for personnel l performing the test. No unreviewed safety or environmental questions are generated as a result of this temporary change.  ;

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76. Safety Evaluation 85-SE Install scaffolding in the Fuel Building rail bay area to facilitate performance of a surveillance test. No unreviewed safety or onvironmental questions are generated as a result of this tm porary change.

77. Safety Evaluation 85-SE Install scaffolding in the Auxiliary Building on the 2047' elevation. No unreviewed safety or envirormental questions are generated as a result of this tmporary change.

78. Safety Evaluation 85-SE Install scaffolding in the Auxiliary Building on the 1988' elevation in the pipe chase area. No unreviewed safety er environmental question,s are generated as a result of this temporary change.

79. Safety Evaluation 85-SE Install scaffolding in Auxiliary Building, area 5, to facilitate the installation of a filter over an exhaust duct inlet. No unreviewed safety or enviromental questions are generated as a result of this tmporary change.

80. Safety Evaluation 85-SE Install a clear 3/8" tubing to read level in the boron recycle holdup tank, THE02B, until a replacement level transmittar is obtained for HE LT-262. No unreviewed safety or environmental questions are generated as a result of this temp 3rary change.

81. JSafety Evaluation 85-SE-39/ Revision 1 - Install two tm porary fire retardant plastic walls with 1mber frames containing two 48" exhaust fans in each wall in the Auxiliary Building, area 5, on the 2090' elevation and situated on a concrete slab. 'Ihe security door will be opened for ventilation and a full time security watch established while door is open. No unreviewed safety or environmental questions are generated as a result of this tmporary charge.

82. Safety Evaluation 85-SE Install scaffolding in the Auxiliary Building on the 2047' elevation near the containment purge radioactive gaseous effluent radiation monitor GP-RE-22 to facilitate rework of damper GL-D-172. No unreviewed safety or envirornental questions are generated as a result of this tmporary change.

83. Safety Evaluation 85-SE Install scaffolding in the Auxiliary Building on the 2047' elevation near containment purge radioactive gaseous effluent radiation monitor GT-RE-22 to facilitate rework of damper GT-D-014. No unreviewed safety or enviromental questions are generated as a result of this tmporary change.

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84. Safety Evaluation 85-SE Install scaffolding in the Auxiliary '

Buildin3 on the 2047' elevation to facilitate rework of danper GIeD- )

- 174. No unreviewed safety or environnental questions are generated as l a result of this temporary change.

85. Safety Evaluation 85-SE Install scaffolding in the Auxiliary Building outside of stairwell #11275 on the 2047' elevation to facilitate rework of danper GF-D-088. No unreviewed safety or environmental questions are generated as a result of this temporary change.

86. Safety Evaluation 85-SE Install scaffolding in the Fuel Building general floor area #6301 in front of door #63031 on the 2047' elevation to facilitate rework of danper GG-D-062. No unreviewed safety or environnental questions are generated as a result of this temporary change.

87. Safety Evaluation 85-SE Install scaffoldin] in the Auxiliary Building, area 5, on the 2026' elevation to facilitate cleaning. No unreviewed safety or environmental questions are generated as a result of this tmporary change.

88. Safety Evaluation 85-SE Install scaffolding in the Auxiliary Building on the 2047' elevation in front of fire door #11273 in the stairwell landing to facilitate rework of danper GF-D-087. No unreviewed safety or environnental questions are generated as a result of this temporary change.

89. Safety Evaluation 85-SE Install scaffolding in the Auxiliary Building on the 2047' elevation near radiation monitor GT-RE-31 and over penetration #99 to facilitate rework of danner GIeD-173. No unreviewed safety or environnental questions arc generatad as a result of this tmporary change.

90. Safety Evaluation 85-SE In= tall scaffolding in the Auxiliary Building on 2026' elevation in the electrical penetration room to facilitate work on danper GF-D-065. No unreviewed safety or environnental questions are generated as a result of this tanporary change.

91. Safety Evaluation 85-SE Originated to reverse the junpers en the logic cards of the status lights associated with the recirculation portion and heaters of the boron injection systs. 'Ihe recirculation portion and heaters are not required to be operable due to boron concentration reduction to 2000 ppn within the system, e.nd consequently have Safety Injection Signal power lifted resulting in anber status light.s on status panels SA066X and SA066Y. 'Ihe Temporary Modification would cause the status lights to be cleared and to turn anber if the cmponents are energized, thus avoiding operator confusion. No unreviewed safety or environmental questions are generated as a result of this temporary change.

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, 92. ' Safety Evaluation 85-SE Install RTD's and thermocouples in existing thermowells to monitor performance of Feedwater heaters. No

- unreviewed safety or enviromental questions are generated as a result of this temporary change.

93. ' Safety Evaluation 85-SE Install plywood to support a laider above the Con ~crol Boan ceiling on west end of the Control Rom. No unreviewed safety or environmental questions are generated as a result of this temporary change.

94. Safety Evaluation 85-SE Block open fire deper GE-D-049 and establish a fire watch until deper rework cmpleted to prevent stem from the miscellaneous condensate drain tank frm entering duct work.

No unreviewed safety or environmental questions are gerrvated as a result of this temporary change.

95. Safety Evaluation 85-SE Defeat the auto open and turbine trip interlock on valves AB FV-23, 25, 27, and 29 and AC IN-134,135,136 and 137 which drain water frm the stem linee following e. turbine trip. 'Iheer valves can be operated manuall' frm the control rom and autmatic owning of these valves causes acontrolled rapid reduction of Reactor C:olant System temperature. No unreviewed safety or envirementa' questions are generatei as a result of this temporary change.

96. Safety Evalu ation 85-SE-55 Replace pipe caps with quick disconnect couplings or two test cnanections on the personnel airlock door seals to simplify the atte.hment of equipment to leak test the seals. No unreviewed t.afety oc environmental questions are generated as a result of this tenoorny c.hange.

97. Safety Evaluation 85-SE Install a blank plate at an existing joint in duct 200-5NL-4 to cut off normal exhaust flow frm the Fuel Building. No unreviewed safety or environmental questions are generated as a result of this temporary change.

98. Safety Evaluation 85-SE Install temporary insulation on check valve BB-V6378B, normal chargirg connection to the Reactor Coolant System, and on flow element BB-FE-427, measurirg the combined flows of the Loop 2 hot and cold leg RID manifolds. Insulation will remain until the next major outage. No unreviewed safety or envirornental questions are generated as a result of this temporary change.

99. Safety Evaluation 85-SE Install scaffoldirs to work on danper GL-D-172 on the 2047' elevation of the Auxiliary Buildirg. No unreviewed safety or environmental questions are generated as a result of this temporary change.

100. Safety Evaluation 85-SE Install scaffolding to reach ducts on suction and discharge of fans CGF03A and B, main steam enclosure exhaust fans, in Area 4 of the Auxiliary Buildirs on elevation 2047'.

No unreviewed safety or environmental questious are generated as a result of this temporary change.

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I 101. Safety Evaluation 85-SE Install scaffolding on elevation 1974' of the Auxiliary Building to clean and insulate various 4" lines in the

- Essential Service Water and Auxiliary Building Heating, Ventilation, .

and Air Conditioning systens to rom coolers SGLO9A and B, SGL10A and '

B, SGL12A and B, and SGL13 A an$ B. Scaffolding was to be installed in only one of two redundant safety equipnent roms at one time. No unreviewed safety or environnental questions are generated as a result of this temporary change.

102. Safety Evaluation 85-SE Install scaffolding in Area 5 of the Auxiliary Building on the 2039' elevation to facilitate cleaning of miscellaneous heating, ventilation and air conditioning equipnent. No unreviewed safety or environnental questions are generated as a result of this temporary change.

103. Safety Evaluation 85-SE Remove covers fra Essential Service Water valve pits to pmp out the pits. Work was to be performed in one bay at a time, leaving the cover in place on the other bay.

Covers were to be replaced if severe weather threatened, or if work was to be suspended for a priod of time. No unreviewed safety or environnental questions are generated as a result of this temporary change.

104. Safety Evaluation 85-SE Install scaffolding on the 2026' elevation of the Auxiliary Building to work on danper GP-D-065. No unreviewed safety or environmental questions are generated as a result of this tenporary change.

105. Safety Evaluation 85-SE Install scaffolding on the 2026' elevation of the Auxiliary Building to repair a void in the concrete.

No unroviewed safety or environnental questions are generated as a result of this temporary change.

l 106.' Safety Evaluation 85-SE Install scaffolding at the west end of wall A in the nort!h Residual Heat Removal pmp rom of the Auxiliary Building on the 1967' elevation. No unreviewed safety or environnental questions are generated as a result of this tenporary change.

107. Safety Evaluation 85-SE Install scaffolding in Arca 5 on the 2047' elevation of the Auxiliary Building to install insulation on toop 3 Main Steanline Isolation valve. No unreviewed safety or environnental questions are generated as a result of this temporary -

change.

108. Safety Evaluation 85-SE Install scaffolding in Ibm 1723 (North Piping Penetration Room) on the 2000' elevation of t.to Auxiliary Building to clean and insulate Essential Fcryice Water system piping.

No unreviewed safety or environnental 'luestions are generated as a result of this temporary chage.

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l 109.. Safety Evaluation 85-SE Install a blank flange in pipe EC 070-

. HCD-4, fuel pool cleanup systen, in the Befueling Watec Storage Tank

- valve pit to facilitate repair of valve BN-V002, at the inlet to the tank. No unreviewed safety or environrr. ental questions are generated as a result of this tenporary change.

110. Safety Evaluation 85-SE Reduction of the Control Rocm air conditioning flow rate to docment noise reduction while maintaining te.nperature at or below 84 degrees F per Technical Specification 4.7.12. No unreviewed safety or enviromental questions are generated as a result of this temporary change.

.111. Safety Evaluation 85-SE Add a 4" connection to the flange between valves AP-V005 and AP-LV-2, condensate storage tank isolation and level control valves, to supply denineralized water to the condensate storage tank, TAP 01, on the normal makeup line for the tank. No unreviewed safety or enviromental questions are generated as a result of this temporary change.

112. Safety Evaluation 85-SE Install a temporary nitrogen supply to tanks IKA 02, 03, 04 and 05, auxiliary feedwater control / main stean atznospheric relief valves accumulators, until pep 1molP returned to normal operation. No unreviewed safety or environmental questions are generated as a result of this temporary change.

113. Safety Evaluation 85-SE Install scaffolding in Poem 1322 (South Piping Penetration Rx2n) on the 2000' elevation of the Auxiliary Building to clean and insulate Essential Service Water system piping.

No unreviewed safety or environmental questions are generated as a result of this temporary charge.

114. Safety Evaluation 85-SE Install a variable speed sheeve on rc 04, Main Control Roan air conditioning unit, to support Contml Hocan Air Conditioning flow reduction. No unreviewed sa H y or environmental questions are generated as a result of this temporary change.

115. Safety Evaluation 85-%M - Install a jmper line to supply nitrogen to safety inject Om accunulator "D", bypassing valve EP-HV-8875D,

' nitronco :.@ ply valve, until this valve is restored to normal  ;

i 0:nic.e. The jmper will run frczn EP-V058, test connection on the l nitrogen header, to EP-V103, drain valve on the level transmitter. No  ;

unreviewed safety or environmental questions are generated as a result .l of this temporary change. '

I 116. Safety Evaluation 85-SE Install scaffolding to high point vent '

I valves NV156 and %V242 in the high pressure coolant injection system thus facilitating parformance of a surveillance test. No unreviewed safety or environmental questions are generated as a result of this temporary change, l

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117. Safety Evaluation 85-SE Install pressure instrmentation on the tube side of High Pressure Feedwiter heaters at existirg pressure

- points AE-V052, AE-V055, AE-V056 and AE-V062. No unreviewed safety or environnental questions are genorated as a result of this tenporary change.

118. Safety Evaluation 85-SE Iastall scaffoldity at Incation TA and T8 (acid neutralizer and degasiff er area) and Incation TA and T3 (railroad bay) on 2000' eleva: ion of Turbine Buildirs. !b unreviewed safety or envirorrnental questions are generated as a result of this tenporary change.

119. Safety Evaluation 85-SE Replace bolts in bonnets of valves AE-V006, suction isolation for Main Feedwater Ptrnp "B", and AE-V009, suction isolation for Main feedwater Ptrap "A", to allow sealant application and stop bonnet. leaks. No unteviewed safety or envirorraental questions aro generated as a result of this tenporary change.

120. Safety Evaluation 85-SE Installation of a tenporary plywood door to support tenporary duct work in the doorway to the Electro-Hydraulic Control Cabinet room in tne Turbine Building. 'Ihe plywood will be l fire--retardant and the anpropriate fire watches will be established.

No unreviewed safety or 2nvirorynental questions are generated as a result of this tenporary change.

131. Safety cvaluation 85-SE Relocation of the weather ra31o in the Control Fean to the weit wall to facilitate radio reception until an outside antenna for tre radio is installed and connected. tb unreviewed safety or onvironmental questions are generated as a result of this tenporary cha.ye.

122. Safety Evaluation 85 -SE Installation of a three-quarter inch carbon steel 30005 rocket welded union in.a drain line fran BM-V-052, Stean Generator Blordown Flash Tank relief valve. No unreviewed safety or envirorsneatal questions are generated as a result of this tenporary change.

123. Safety Evaluation 85-SE Installation of scaffoldirg in the Auxiliary Buildirs to facilitate cleanirg and insulating Essential Service Water system piping. 'Ihe ccaffoldity will not be tied to, or directly over, any safety-related equipnent, ard will be inspected prior to conmer.cing work. No unreviewed safety or envirorsnental questions are generated as a result of tais tenporary change.

124. Safety Evaluntion 8.5-SE Installation of scaffolding in the Auxiliary Building to facilitato cleaning ard insulating Essential Service Water systen piping. No unreviewed safety or envirortrental questions c.re generated as a result of this tenporary change.

125. Safety Eviduation 85-SE Installation of ccaffoldiry in the Auxiliary Building to facilitate cleanirg and insulating Essential Service Nater system pipirg. tb unreviewed safety or environnental questior.s are generated as a result of this tenporary charge.

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126. . Safety Evaluation 85-SE Installation of tmporary blank flanges in place of the tube side relief valve, BM-V-701, on the Steam

- Generator Blowdown Regenerative Heat Exchanger. Overpressure protection will be provided by BM-V-702, tb unreviewed safety or environnental questions are generated as.a result of this tmporary change.

127. Safety Evaluation 85-SE Installation of scaffolding in contaiment on elevation 2026' to facilitate repair of feedwater check valve AE-V-122. No unreviewed safety or environnental questions are generated as a result of this tmporary change.

120. Safety Evaluation 85-SE Allow the replacement of bonnet bolts on valves AE-V-0006, suction isolation valve for Main Feedwater Pmp "B",

and AE-V-0009, suction isolation valve for Main Feedwater Pmp "A",

with bolts designed to allow sealant application. No unreviewed safety or enviromental questions are generated as a result of this temporary change.

129. Safety Evaluation 85-SE Replacement of broken U-bolt on hanger AD06-H015/432, supporting the suction line to Main Pendwater Pump "B",

with a surplus U-bolt frm hanger AD06-H014/431. No unreviewed safety or environmental questions are generated as a result of this tmporary change.

130. Safety Evaluation 85-SE Allow the use of a rupture disc on the Hydrogen Recmbiner in the Gaseous Radwaste System that does not have the proper pricing documentation on the Purchase Order. No unreviewed safety or environmental questions are generated as a result of this temporary change.

131. Safety Evaluation 85-SE Installation of a tm porary pressure gauge to replace a failed accumulator pressure transmitter on a Main Steanline Isolation valve. @ e failed trans itter functioned only for Control Rocm iMication, and the temporary gauge will serve the same purInse, only with local indication. Ib unreviewed safety or environnental questions are generated as a result of this temporary change.

132. Safety Evaluation 85-SE Installation of a jmper acrosa a contact point on relay ]XEF33 to allow the circuit. to perform its design function by starting Essential Service Wacer pump "A". %e relay is an interposing relay which pemits the cf reuit breaker to close on a IoM Sequence or Auxiliary Feedwater loss of Suction Pressure signal.

No unreviewed safety or environmental questions are generated as a result of this tenporary chanje.

133. Safety Evaluation 85-SE Originated to return the Auxiliary Feedwater Ptrap discharge control valve, AIrHV-9, to service with danage to the teminal block on the circuit board. % e damage consists of a broken flash guard between tw teminals, one of which is not used, aM a hairline crack across one teminal point, but there is no potential for arcing. No unreviewed safety or enviromental questions are generated as a result of this temporary change.

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134. Safety Evaluation 85-SE Originated to fabricate a hot tool roca in the Auxiliary Building at elevation 1974'. We rom panels present

- no seismic concerns and no essential equipment is endangered by the panels. No unreviewed safety or enviromental questions are generated as a result of this temporary change.

135. Safety Evaluation 85-SE Originated to allow trained personnel other than the Shift Supervisor, or his designee, to imp 1 ment the Ignition Source Permit system. No unreviewed safety or enviromental questions are generated as a result of this temporary change.

136. Safety Evaluation 85-SE Installation of tmporary clamp and addition of sealing cmpound to the hand hole flanges of AE-FE-510 and 520, Main Feedwater system flow venturies. No unreviewed safety or enviromental questions are generated as a result of this tmporary change.

137. Safety Evaluation' 85-SE Originated to allow test flange downstreau of valve BG-V-526, Seal Water Injection Filters Inlet Drain Valve, located in Centrifugal Charging Pmp Bom "B", to reain installed and to allcw the use of Swagelock fittires in place of a permanently installed blind flange. W e Swagelock fittings have a

, higher pressure ratirg than the blind flange.. No unreviewed safety or envimmental questions are generated as a result of this temporary change.

138. Safety Evaluation 85r-SE Originated to establish a tmporary flowpath frm the recycle evaporator concentrates discharge to the spent fuel trol to allow boration evolutions of the spent fuel pool while the transfer canal is dry and isolated frm the spent fuel pool by the spent fuel pool gate. % e flow path was established so as to minimize any potential siphoning effects and is to be removed prior to placment of any fuel within the spent fuel nol. I No unreviewed safety or environmental questions are generated as a result of this tempora q change.

139. Safety Evaluation 85-SE-100 - Originated to establish a temporary flowpath from the recycle evaporator concentrates discharge to the spent fuel pool to allow boration evolutions of the spent fuel pool while the transfer canal is dry and isolated from the spent fuel pool by the spent fuel pool gate. W e flow path was established so as to minimize any potential siphonirn effects arx3 is to be removed prior to placement of any spent fuel within the spent fuel pool. No unreviewed safety or envirormental qumtions are generated as a result of this tmporary change.

140. Safety Evaluation 85-SE-101 - Originated' to F. low the installation of a non-safety related gasket in a pmp in the Boron Recycle Systs.

%e replacment gasket satisfies the pmp rr.q. uirments, and is to be used until it can be qualified or a qualified replacement is obtained. Integrity of leak tightness will be achieved by the use of this gasket. No unreviewed safety or enviromental questions are generated as a result of this tmporary charge.

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141. Safety Evaluation 85-SE-102 - Addition of piping to the plant heating system to allow on-line addition of corrosion inhibitors to the

- systen. No unreviewed safety or environmental questions are generated as a result of this temporary change.

142. Safety Evaluation 85-SE-103 - Originated to allow plant operation with a differential tenperature across the condenser of 38 degrees Fahrenheit until an inoperable circulating water pump could be returned to service. Wis increase does not affect the functional capabilities of the Essential Service Water Systen. W is situation poses no environnental concerns due to the maximun discharge tenperature allowed and the season in question, early fall. No unreviewed safety or environmental questions are generated as a result of this tenporary change.

143. Safety Evaluation 85-SE-104 - Installation of tenporary puap skids for tenporary fire pumps due to the permanent diesel fire punp being inoperable. No unreviewed safety or environnental questions are generated as a result of this tenporary change.

144. Safety Evaluation 85-SE-105 - tbdification of the Nuclear Stean Supply Systen aM Balance of Plant canputer data bases to set the allowed deviation between shutdown bank and shutdown rod position to the expected deviation of 96 when any shutdown bank is between 18 and 210 steps (ttansition range) . W is change will avoid nuisance alarm conditions during normal plant transitions. No unreviewed safety or enviro 1 mental questions are generated as a result of this change.

145. Safety Evaluation 85-SE-106 - During plant normal operations, the containment internal pressure is maintained within Technical Specificaticn limits by the Contairunent Mini Purge Synten. With the Containment Mini Purge Exhaust subsysten out of service for maintenance and/or testing, an alternate method for wnting the containnent is needed. A procedure, SYS GS-200, "Containnent Pressure Reduction using the Hydrogen rurge Subsystem", for ver, tin) the containnent through a 4" pipe in the Containnent hydrogen Control System into the Auxiliary Building Heating, Ventilatirg, and Air Conditioning Systen was created for this purpose. %ere are no unreviewed safety or enviremental questions generated as a result of this alternate method for contairment ventin).

146. Safety Evaluation 85-SE-107 - Due to increased usa 3e of service air aM fregaency of repair of the service air conpressors, a tenporary compressor was added to the systen through valve KA-V104. This tenporary change generates no unreviewed safety or envirorsnental questions.

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147. Safety Evaluation 85-SE-108 - During maintenance on a Mini Purge Exhaust valve Gr-HZ12, a seisnic hanger on the ductwork outside the

- contalment was pinned to establish a safe and structurally sound support to the ductwork, thus minimizing the potential for danage during repair activities. @is removed the seisnic qualification of

. the hanger and duct which results in a breach of contaiment outside boundary. However, the repair activity on the valve itself was also a breach of the containment outside boundary. We inside boundary was blocke3 and maintained. Technical Specification 3.6.1.7 Action Statenent c, which allows continued operation for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in this configuation, was in effect. We pin was removed and seismic qualification of the duct work was restored prior to returning the Mini Purge Exhaust Systen to operable status. No unreviewed safety or enviromental questions were generated as a result of this temporary change.

148. Safety Evaluation 85-SE-110 - Originated to allow the lifting of a i lead frun radiation monitor BM-RT-25 to prevent the initiation of a l

Stean Generator Blowdown Isolation Signal while troubleshooting was

, being performed. Autmatic actuation of the Stean Generator Blowdown

! Isolation valves remained available via redundant radiation monitors

! SJ-RE-02 and DM-RE-52. No unreviewed safety or environmental questions are generated as a result of this temporary modification..

l 149. Safety Evaluation 85-SE-111 - Originated to allow the attachment of a

. hose to the leakoff line on valve LF-W-96, contaiment outside l isolation valve in the line leaiing fran the contaiment normal sunps l to the floor drain tank. We addition of the drain hose is for the l purpose of routing leakage to the floor drain to avoid contaminatirv3 I the floor, and does not affect operation of the subject valve, or any otlyer omponent. No unreviewed safety or environmental questions are geherated as a result of this temporary modification.

150. Temporary Modification 84-329-SB - Temporary replacement of safety-related card edge connectors located in process protection cabinet.

No unreviewed safety or environmental questions are generated as a result of this change.

151. Temporary Madification 85-95-HB - Installation of a tenporary 0-ring in a Liquid Radwaste Systen punp. No unroviewed safety or l enviromental questions are generated as a result of this change.

152. Temporary Modification 85-155-CC - Renove gauge CC-GFA-7 and install instrunent air supply hose fran KA-V466, to supply instrunent air to generator casing. No unreviewed safety or enviromental questions are generated as a result of this change.

l 153. Temporary Modification 85-172-RR - Installation of adapter cables on l the Safety Paraneter Display System (SAS) and Onergency Response Facility Information System (ERFIS) data links. No unreviewed safety oi environmental questions are generated as a result of this charije.

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154. .'Ibnporary redification 85-176-BB - Installation of temporary 0-ring on Reactor Coolant System pressure transmitter BB-PT-0405. Ib unreviewed

, safety or enviromental questions are generated as a result of this change.

155. Temporary tbdification 85-204-EC - Installation of flush radaptors on fuel pool cooling valves EC-V037, DC-V043, and Er-V104 to allow draining of domineralized water fran the spent fuel pool. 'Ihis temporary modification was reviewed and it was deterinined that no unreviewed safety or enviromental questions are generated as a result of this change, provided the flush adapters are reraoved prior to the first refueling outage.

156. Temporary Modification 85-231-BB - Removal of the keeper pin frm the top of the connecting rod of valve BB-PCV-455B to facilitate maintenance. 'Ib be used as is until first outage. tb unreviewed safety or enviromental questions are generated as a result of this change.

157. Tmporary Pbdification 85-232-GK - Replacement of chlorine monitor GK-AITS-002 with monitor KT-AITS-11 while awaiting replacement parts. tb unreviewed safety or environnental questions are generated as a result of this chan3e.

158. Temporary Modification 85-240-BB - Use lockwire to fasten together incore thermocouple connector on BB-TE-05 tmperarily. tb unreviewed safety or enviromental questions are generated as a result of this change.

159. Temporary tbdification 85-246-GL - Install scaffolding for rework of danper GT-D057. tb unreviewed safety or enviromental questions are generated as a result of this change.

160. Tmporary Modification 85-255-AB - Install scaffolding around Stean Generators to facilitate the encapsulation of instrtsr.ent isolation root valves. tb unreviewed safety or environnental questions are generated as a result of this change.

161. Temporary Modification 85-504-WS - Originated to allow the installation of temporary drain lines, along with the associated fittin3s and valves, on Service Water System Strainers lWS01FA & B.

No unreviewed safety or environnental questions are generated as a result of this tmporary nodification.

162. Temporary Procedure Change Form 4MA 85-798 to SU8-BB13, Rev. 0 -

" Reactor Vessel Level Indication System". - Written to allow for the collection of additional data with different canbinaticrs of Reactor i Coolant Ptsnpa runnin3 No unreviewed safety or environmental questions are generated as a result of this change.

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163.~ Tenporary Procedure Change Ebrm #MA 85-878 to SU8-BB13, Rev. O, ,

" Pressurizer Relief Valve Test" - Written to allow testing to be - i performed at a lower temperature. %e lower Reactor Coolant Systen j tenperature will not affect the test results. No unreviewed safety or  !

environmental questions are generated as a result of this change.

164. 'D sporary Procedure Change Form #MA 85-894 to SU8-BB13, acv. 0 -

• Pressurizer Relief Valve Test" - Written to allow test s instrunentation change from digital thermameter to a surface pyroneter. W is test instrunent will be used for trending purposes only. No unreviewed safety or environmental questions are generated as a result of this change.

165. Engineering Evaluation Request 85-GK-ll - Originated to allow the use of a different model hydramotor actuator on valve GK-V-766 in the Centrol Building Heating, Ventilation, and Air Conditioning System in place of an inoperable actuator. % is valve controls the Essential Service Water cooling water flow to the Control Iban Air Conditioning Unit, SGK04B. Both models are qualified envircrrnentally and seisnically for safety related applications outside containment. %is change was made permanent by the approval of Plant Modification Request 01388. No unreviewed safety or environmental questions are generated as a result of this change.

166. Field Change Notice (FCN) SAPM 10730 - Replacement of three NRC-4 relay cards in the 7300 process control cabinets with NRC-ll cards.

, No unreviewed safety or environnental questions are generated as a result of this change.

167. Procedure Change - We criteria for detector response were changed in the Initial Core Ioading Sequence procedure. Details were transnitted under separate cover. No unreviewed safety or environnental questions are generated as a result of this change.

368. r oposed Revision to Technical Specification 3.6.1.6, " Containment Vec sel Structural Integrity" - We proposed revision would alter the surveillance requirements for verifying the operability of the tendon sheathing filler grease and allow the classification of certain situations as possible abnormal degradation and allow an engineering evaluation to be performed which may demonstrate continued containnent structural integrity. It was determined that the proposed Technical Specification change, should it be implemented, will not impact tendon integrity since tendon integrity will be assured by surveillance of renaining paraneters and restoration of parameters or assurance by engineering evaluation; will not affect the method and manner of plant operation; and will not affect camponents and equipnent important to safe operation. Werefore, the proposed snendment does not create the possibility of a new and different accident fran any previously evaluated.

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KANSAS GAS AND ELECTRIC COMPANY THE E.LECTF#C COMPANY l

l l

I OLENN L MOESTER VtCE .#El* DENT a NwC AE A#

March 11,19%

Mr. R. D. Martin, Regional Administrator U. S. Nuclear Regulatory Commission Region IV ,

611 Ryan Plaza Drive, Suite 1000 l Arlington, Texas 76011 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555 KMLNRC 86-040 j Ret Docket No. STN 50-482 Subj Wolf Creek Generating Station )

Annual Safety Evaluation Report Gentlemen:

Attached is the Annual Safety Evaluation Report for Wolf Creek Genertting Station which is being submitted pursuant to 10 CFR 50.59 (b). This report l covers the period of March 11, 1985, to December 31, 1985.

Very truly yours,'

wh (L Glenn L. Koenter Vice Presiderat - Nuc car GLK see Attachment cc P0'Connor (2)

JCummina

.iTaylor 0

i 40 201 N. Market - Wictuts, Kanses - Med Address: PO. Don 208 i Wicturn, Kansas 6720 t - Telephone Area Code (3 t 61 26164 $ 9