ML20195B584
| ML20195B584 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 06/14/1988 |
| From: | Schnell D UNION ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| ULNRC-1788, NUDOCS 8806210459 | |
| Download: ML20195B584 (70) | |
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Umov Etscraic a
1901 Gratiot Street SL Lova Donald F. Schnell Vce Presdent U.
S.
Nuclear Regulatory Commission Attn Document Control Desk Washington, D. C.
20555 ULNRC-1788 Gentlemen:
DOCKET NUMBER 50-483 CALLAWAY PLANT 10CFR50.59 ANNUAL REPORT SUMMARIES UNION ELECTRIC APPROVED WRITTEN SAF,ETY EVALUATI,0N,S,
Reference:
ULNRC-1524, dated June 5, 1987 In accordance with 10CFR50.59, this letter transmits a report which summarizes written safety evaluations of changes approved and implemented for callaway Plant since the reference repor t and through April 30, 1988.
The repor t format is presented as follows:
O Report item number O
Safety evaluation ID number O
Title and descriptive text which summarizes the safety evaluation All items reported herein were determined to not involve an unreviewed safety question. provides a key to the sources of the changes which are provided in this report.
If there are any questions', p tease contact us.
Very truly yours Donald F.
Schnell DJW/skn Attachments 8806210459 800614
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PDR A' JOCK 05000483
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Maila%, $ddress: P,0. Box 149, St Louis, MO 63166
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cc Gerald Charnoff, Esq.
Shaw, Pittman, Potts & Trowbridge 2300 N.
- Street, N.W.
Washington, D.C.
20037 Dr.
J. O. Cermak CFA, Inc.
4 Professional Drive (Suite 110)
Gaithersburg, MD 20879 R. C.
Knop Chief, Reactor Project Branch 1 U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Bruce Little Callaway Resident Of fice U.S.
Nuclear Regulatory Commission R5fl
- toedman, Missouri 65077 Tom Alexion (2)
Of fice of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Commission Mail Stop 316 7920 Norfolk Avenue Bethesda, MD 20014 Manager, Electric Department Missouri Public Service Commission P.O. Box 360 Jefferson City, MO 65102 U.S.
Nuclear Regulatory Commission ATTN:
Document Control Desk Wachington, D.C.
20555
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ATTACHMENT 1 ULNRC-178 8 JUNE 1988 l
REFERENCE KEY l
Reference Description CMP f Callaway Modification Package (Design Change)
RMP f Restricted Modification Package (Design Change)
CN f,SP FSAR Change, Standard Plant CN f, SA FSAR Change, Site Addendum OL f Technical Specification Change CDP f Chemistry Department Administrative Procedures ETP f Engineering Technical Procedures OTN f Normal Operating Procedures OTS f Special Operating Procedures RTN f Radwaste Normal Operating Procedures RTO #
Radwaste Off-Normal Operating Procedures RCA 9 Request for Corrective Action RFR f Request for Resolution TOPRP Turbine Overspeed Protection Reliability Program MISC Safety Evaluations per formed for isolated items or activities Note:
PSAR and Technical Specification changes are also repor ted under 10CFR50.71 and 10DFR50.90 as applicable.
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13CF050.59 ANNUGL QEP00T SUQMAR2ES OF UNION ELECTOIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 1
NE-66-2J32 CMP 36-JJ23 REPLACED BARTON PRESSURIZER PRESSURE TRANSMITTERS WITH T,08AR MODEL CMP 86-2233 REPLACED BARTON PRESSURIZER PRESSURE TRANSMITTERS WITH TO94R MODEL TRANSMITTERS. TOBAR TRANSMITTERS MEET OR EXCEED REQUIRE 1ENTS OF ORIGINAL ONES AND ARE ENVIRONMENTALLY CUALIFIED. REPLACEMENT WAS NECESSARY OUE TO HIGH 8ARTON TRANSMITTER FAILURE RATE.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OA CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EV ALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTI OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION i
ITEM ID 2
OA-84-JJ83 CMP S4-0523 ADDED CHECK VALVES TO CENTRIFUGAL CHARGING PUMP LINES.
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CMP 54-8523 ADDED CHECK VALVES TO CENTRIFUGAL CHARGING PUMP LINES. THE CHANGE ADDED ?JO THREE INCH CHECK VALVES TO CENTRIFUGAL CHARGING PUMPS DISCHARGE LINE l
DOWNST*EAM OF VALVES BG-8433 A AND C ALONG WITH THE APPROPRIATE HANSERS.
l I
(THIS CHANGE IS PARTIALLY IMPLEMENTED.)
PURSUANT TO THE AB0VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSECUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-I MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-l PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY I
CUESTION DID NGT EXIST.
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1BCFR52.59 ANNUAL REPORT SUMMARIES OF U3 ION ELECTRIC APDROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 3
NE-6$-J057 OL 1341 REVISED OPERASILITY AND SURVEILLANCE REQMTS FOR RX TRIP BREA,KERS OL 1241 REVISED OPERASILITY AND SURVEILLANCE REQUIREMENTS CONCERNING REACTOR TRIP BREAKERS IN ORDER TO COMPLY WITW NRC STAFF GUIDANCE CONTAINED IN GENERIC r
LETTER 85-39 DATED 5-23-85. COMPLIANCE WITH THE GENERIC LETTER PROVIDES ADDI-TIONAL CONTROLS TO ENSURE PLANT SAFETY. THIS CHANGE WAS APPROVED SY THE NRC IN LICENSE AMENDMENT-19.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN L
PR09A91LITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT
OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY 45 DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY I
QUESTION DID NOT EXIST.
I REPORT SAFETY EVALUATION ITEM ID 4
NE-36-J186 OL 1950 REVISED TECH SPEC TABLES 3.5-6 AND 3.3-13 FOR CONTAIN. ATM35. RAD.MONITO i
OL 1250 REVISED TECH SPEC TABLES 3.3-6 AND 3.3-13 FOR CONTAINMENT PURGE ISOLA-l TION TRIP FUNCTION OF THE CONTAINMEhi ATMOSPHEPE RADIATION MONITORS. THE REVI-I SION DELETED THE TRIP FUNCTION WHILE RETAINING THE INDICATION AND ALARM FUNC-TIONS FOR RCS LEAKAGE DETECTION. BOTH CONTAINMENT PURGE FADIATION M3NITORS WERE REVISED TO BE OPERABLE AT ALL TIMES TO MEET SINGLE FAILURE CRITERIA. AN ALLOW-AhCE FOR ONE INOPERABLE PURGE MONITOR ALLOWS FOR PERFORMING TEST AND MAINTEN-ANCE ACTIVITIES. REDUNDANT CONTAINMENT ATMOSPHERE RADIATION MONITORING IS ALSO PROVIDED BY HIGH RANGE POST-ACCIDENT MONITORS. CHANGE WAS APPROVED BY THE NRC IN LICENSE AMENDMENT-20.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE 04 CONSEQUENCF% OF AN ACCIDENT OR MALFUNCTION OF EQUIP-l MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTI 04 CREATE POSSIBILIT' FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE SASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY
(
QUESTION DID NOT EXIST.
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10CFR58.59 ANMUAL REPORT SUMMARIES OF UNION ELECTOIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 5
NE-37-01J1 ETP-AL-ST3J1 PROCEDuaE TESTED AUX.FEEDJATER PUMPS FOR MAX.0PERATING,DIFF. PRESS.
ETP-AL-ST2J1 PROCEDURE WAS DEVELOPED TO TEST THE SUCTION VALVES TO THE AUX.
FEEDWATER PUMPS AGAINST MAXIMUM OPERATING DIFFERENTIAL PRESSURE. THE PROCEDURE REQUIRED PLACING THE AUX. FEEDWATER SYSTEM IN A CONFIGURATION IDENTICAL TO NORMAL OPERATION WITH THE EXCEPTION OF A DOWNSTREAM VENT 3EING CYCLED OPEN TO PLACE DIFFERENTIAL PRESSURE ACROSS THE SU8 JECT MOTOR-OPERATED VALVES. THE TEST PROCEDURE REQUIRES PERFORMANCE IN MODE 5 WHEN THE AUX.FEEDWATER SYSTEM IS NOT REQUIRED PER TECH SPECS.
PURSUANT TO THE A30VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBAdILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY GUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 6
NE-dT-J1J2 CN 451 SP 6.2.1,12.3 REVISED FSAR TO DELETE TEAR STRIPS FROM WATER 8AG DESIGN CN 451 AEVISED THE FSAR SP SECTIONS TO DELETE TEAR STRIPS FROM WATER 8AG DESIGN.
THE ORIGINAL TEAR STRIPS WERE PROVIDED AS A PROTECTIVE MECH 4hISM AGAINST DYNAMIC LOADS FROM A POSTULATED RUPTURE OF RCS PIPING IN THE REACTOR CAVITY. WITH THE REVISED GDC-4 REQUIREMENT AND THE ' LEAK-BEFORE-BREAK' CONCEPT,CALLAWAY HAS DEMONSTRATED COMPLIANCE WITH THE REVISED GDC-4rEXCLUDING DYNAMIC EFFECTS AND HENCE DELETION OF THE TEAR STRIPS. IN ADDITION SOME WATER 9AGS MAY HAVE BEEN PURCHASED JITH ALUMINUM FEMALE "ITTINGS. THE ADDITION 4L ALUMINUM IN CONTAINMENT DUE TO WATER BAG FITTINGS IS EaVELOPED BY THE FSAR IN-CONTAINMENT ALUMINUM INVENTORY.
PURSUANT TO THE A90VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE 04 CONSEQUENCES OF AN ACCIDENT OR M ALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTJ OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS In THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTI0h DID NOT EXIST.
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1dCFR50059 ANNUAL QEPORT SUMMARIES OF UN20N ELECTREC APPOOUED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID l
7 NE-84-JJ61 CMP S4-0235 DELETED CHLORINE M3NITORS G(AITS2,4XAITS3 AND CONTROL 80,4R0 INDFC.
CMP 84-0235 DELETED CHLORINE MONITORS GKAITS2,GKAITS3 AND THE ASSOCIATED COM-TROL 80Aeo INDICATORS. THE MONITOR $ ARE NOT REQUIRED FOR PLANT OPERATION SINCE CALLAWAY HAS kJ POTENTIAL FOR CMLORINE GAS HAZARD. THE CHANGE DOES NOT ADVERSE-l LY IMPACT PLANT SAFETY. THE CHANGE REVISED FSAR FIG. 9.4-1.
y PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBA3ILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OWER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE l
OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
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Tf f E EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY Q*lESTION DID NOT EXIST.
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REPORT SAFETY EVALUATION ITEM ID 8
NE-$6-J132 CMP 86-2c63 ADDED DRAIN LINES TO FEEDWATER BYPASS CONTROL VALVES F
CMP 86-3263 ADDED DRAIN VALVES 3ETWEEN ISCLATION VALVES FOR THE FEEDWATER BYPASS CONTROL VALVES. CHANGE INVOLVED A NONSAFETY RELATED SYSTEM AND RESPONDED TO PERSONNEL SAFETY CONCERNS.
PUR$UANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE CR CONSEQUENCES OF AN ACCIDENT OR MAL 8 UNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT, 04 REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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l 1JCFR50.59 ANNUAL REPGRT SUMMARIES OF UNION ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION L
ITEM ID 9
NE-d$-J134 QL 1025 REVISED TECH SPEC SECTION 3/4.8.1.1 FOR D/G SURVEILLANCE REQUIREMENTS l
l CL 1J25 REVISED TECH SPEC SECTION 3/4.8.1.1 FOR D/G SURVEILLANCE REQUIREMENTS TO IUCREASE RELIABILITY AND REDUCE STRESS AND WEAR ON THE D/G ENGINES. CHANGES L
l IMPACT TIMING OF INITIAL AND REPEAT START TESTS; FREQUENCY OF FAST LOADINGS (ELIM-j IAATED EXCEPT ONE PER 6 MONTHS AND 16-MONTH REFUELING TESTS); ROUTINE SURVEIL-L LANCE TEST LOADING TO 62% OF CONTINUQUS RATED LOAD; ENGINE PRELUBE AND VENDOR RECOM.1 ENDED WARMUP PROCEDURES REQUIRED FOR ALL D/G TEST STARTS; REDUCTION IN AMOUNT OF ACCELERATED TESTING BASED ON A RELIA 91LITY GOAL OF 0.95 PER D/G; REDUCE FAILURE COUNT TO ZERO AND RESET TEST FREQUENCY TO A 31 DAY INTERVAL IF A MAJOR ENGINE OVERHAUL AND TEST SERIES COMPLETED. CHANGES ARE 3ASED LARGELY ON RECOM-MENDATIONS FROM CFNERIC LETTER 84-15, AND WERE APPROVED BY THE NRC IN LICENSE AMENDMENT-21.
PURSUANT TO THE ASOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PR09 ABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETV OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DE81NED IN THE BASIO FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EWALUATION ITEM ID 10 NE-5$-0137 OL 1355 REVISED TS SECTIONS 5.3,5.6, FIG 3.9-1 TO INCLUDE CHANGE TO VANTAGE FUEL F
OL 1255 REVISED TS SECTIONS 5.3,5.0,AND FIGURE 3.9-1 TO INCLUDE A DESIGN CH ANGE TO VANTAGE FUEL. CHANGES INCREASED MAXIMUM SPENT FUEL POOL STORAGE LIMIT TO 4.25W/2 U235. FIGURE 3.9-1 NOW INCLUDES VANTAGE FUEL AS WELL AS STANDARD AND OFA FUEL TYPES.
CRITICALITY CALCULATIONS WERE PERFORMED TO VERIFY THAT VANTAGE FUE IS MEUTRONICALLY SIMILAR TO OF4 FUEL AND EMISTING MARGINS ARE ADE3UATE FOR STOR-ING FUEL AT THE HIGNER ENRICHMENT. CHANGES WERE APPROVED SY THE NRC IN LICENSE AMENDMEMT-23.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR C01 SEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITT FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE r'
OVER PREV!0US EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR EMDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
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THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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13CFR52.59 QNNUQL OiP30T SUMMORIES r
0F UNION ELQCTOIC OPPQ0VED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 13 NE-57-J;53 CN 446 REVISED FSAR SP SECTION 10.3.5.1 FOR SECONDARY WATER CHEMISTR,Y GUIDELINE CN 464 REVISED FSAR SP SECTION 10.3.5.1 FOR SECONDARY WATER CHEMISTRY GUIDELINES THE CALLAdAY SECONDARY WATER CHEMISTRY PROGRAM AND GUIDELINES ARE DESIGNED TO MEET THE INTENT OF THE EPRI PWR SECONDARY WATER CHEF.ISTRY GUIDELINES AND THE WESTINGHOUSE GUIDELINES FOR SECONDARY VATER CHEMISTRY. THIS SECTION OF THE FSAR WAS REVISES TO REFERENCE THE COMMITMENT TO THE EPRI AND WESTIhGHOUSE GUIDELINES AND TO REMOVE THE REFERENCE TO BRANCH TECHNICAL POSITION MTES 5-3. THE CALLAWAY SECONDARY CHEMISTRY PROGRAM MEE?a THE INTENT OF BYP MTE9 5-3 AND THE REVISED COMMITMENT CONTAINS CURRENT TECHNICAL RECOMMENDATIONS AND GUIDELINES WHICH ARE MORE UP-TO-DATE AND COMPREHtNSIVE THAN STP MTE9 5-3, DATED JULY 1981.
PURSUANT TO THE As0VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPONTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTI OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT! OR REDUCE THE MAR-GIN OF SAFETY AS D2 FINED IN THE 8 ASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATE 0N DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
e REPORT SAFETY EVALUATION ITEM ID 14 NE-57-J062 CMP 86-1215 CHANGED FUNCTION OF PRESSURIZER ROOT VALVES TO 9EDEGREE ELBOW CMP 86-1J15 REMOVED VALVE INTERNALS OF PRESSURIZER ROOT VALVES BE-V-0J99,122,
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AND 105, AND REPLACED THEM WITH A MACHINED PLUG WELDED IN PLACE. THE FUNC-TION OF THE VALVE WAS CHANGED TO A 9CDEGREE ELBOW. CHANGE ELIMINATES PROBLEMS WITH LEAKING PRESSURIZER ROOT VALVES. THE VALVES ORIGINAL FUNCTION WAS TO I
PROVIDE INSTRUMENT ISOLATION FROM THE MAIN PROCESS. THE DESIGN OF THE MACHINED PLUG PROVIDES A MORE CONSERVATIVE STRESS AND SEISMIC ANALYSIS SY REDUCING THE MASS OF THE VALVE CONFIGURATION AND DECREASING ECCENTRIC LOADING BY MOVING THE CENTER OF GRAVITY If; A CONSERVATIVE DIRECTION. THIS MODIFICATION DECREASES PI-PING STRESSES. FSAR ANALYSES REMAIN BOUNDING.
PURSUANT TO THE ASOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OWE 3 PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-
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PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY JUESTION DID NOT EXIST.
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ANNUAL REPORT SUMMARIES L
OF UNIOM ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS P
REPORT SAFETY EVALUATION ITEM ID 15 NE-87-0J63 OL 1061 AMENDMENT REQUEST REVISED ESF RESPONSE TIMES FOR SI SIGNAL I,NITIATORS CL 1061 AMENDNENT REQUEST REVISED TECH SPEC ESF RESPONSE TIMES FOR CONTAIN-MENT HIGH PRESSURE 1, LOW PRESSURIZER PRESSURE, AND LOW STEAMLINE PRESSURE TO REFLECT THE VALVE INTERLOCK IN THE SAFETY INJECTION SYSTEM BETWEEN VOLUME CON-TROL TANK ISOLATION VALVES AND REFUELING WATER STORAGE TANK ISOLATION VALVES.
SENSITIVITY ANALYSES VERIFY THE ACCEPTABILITY OF THE ADDITIONAL 15SEC TIME DELAY. THE DELAY IN AVAILABLE BORATED WATER OCCURS EARLY IN THE STEAMLINE SREAK TRANSIENT AND THE ANALYSES SHOW SMALL CHANGES IN FINAL RESULTS. FSAR ANALYSES REMAIN BOUNDING. THE CHANGES WERE APPROVED eY THE NRC IN LICENSE AMENDMENT-22.
PURSUANT TO THE ADOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS Ih THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT 1YPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION LTEM ID to 4,E-6 7-J 116 ETP-G8-030J1 PROCEDURE PERFORMS FLOW BALANCE TEST FOR CHILLED WATER SYS COCLERS ETP-G8-03031 PROCEDURE PERFORMS A FLOW BALANCE TEST FOR PROPER FLOW THROUGH ROOM COOLERS IN THE CENTRAL CHILLER SYSTEM. THIS IS A NONSAFETY-RELATED SYSTEM WHICH IS NOT REQUIRED FOR SAFE SHUTDOWN OR MITIGATION OF A DESIGN BASIS ACCI-DENT.
PURSUANT TO THE A30VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE EArETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS 1N THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY GUESTION DID NOT EXIST.
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13CFR50.59 ANNUAL REPORT SUMMARIES r
OF UNIOM ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 17 NE-37-0117 OTS-BG-030J2 PROCEDURE PERFORMED CHECK VALVE BACK FLOW LEAKAGE TESTC,BG-V-589)
OTS-BG-00332 PROCEDURE PERFORMED BACK FLOW LEAKAGE TEST ON CHEMICAL AND VOLUME COJTROL TRAIN S CHECK VALVE (8G-V-589). TEST DEMONSTRATED LEAKAGE TO BE LESS THAN 10GPM. THE TEST METHOD UTILIZED THE SAFETY IhJECTION TEST HEADER AS A FLOW-PATH. THIS METHOD RESULTS IN CONDITIONS ON THE TEST HEADER NO DIFFERENT THAN EXPERIENCED DURING INTER-SYSTEM LOCA CHECK VALVE TESTING. TRAIN 8 IS ISOLATED FROM TRAIN A 0F THE CVCS SY AT LEAST ONE ISOLATION VALVE ON EACH LINE AFFECTED BY THE PROCEDURE. IF BG-V-589 SHOULD FAIL OPEN, LOSS OF CVCS TRAIN A INVENTORY WOULD BE PREVENTED BY CLOSING HIGH PRESSURE COOLANT INJECTION VALVES. THE TEST METHOD CONFORMS TO TECH SPECS AND ASSOCIATED ACTION STATEMENTS.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MLLFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
,THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 18 NO-85-JJ43 CMP 85-0233 REDESIGNED OVERPRESSURE PROTECTION FOR THE CONDENSATE POLISHERS CMP 85-0233 INSTALLED OVERPRESSURE PROTECTION FOR THE CONDENSATE DEMIN SYSTEM TO P 7TECT THE CONDENSATE POLISHERS FROM PRESSURE SPIKES IN THE SYSTEM DURING NC.
. s. OPERATION. THE CONDENSATE DEMIN SYSTEM IS NOT SAFETY-RELATED.
PURSUANT TO THE A60VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-NENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER P R E V.* 0 U S EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
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THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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10CFR5905D ANNUAL REPORT SUMMARIES 0F UNION ELECTRIC APPROVED g
WRITTEN SAFETY EVALUATIONS r
REPORT SAFETY EVALUATION ITEM ID 19 NE-37-20J1 CMP 35-3356 ADDED A REDUNDANT FAN COIL UNIT IN THE MG SET ROOM CMP 85-0356 INSTALLED A FAN-COIL COOLING UNIT INSIDE THE ELECTRICAL EQUIPMENT ROOM ON 2026 ELEVATION OF THE AUX. BUILDING. THE UNIT SUPPLEMENTS THE EXISTING COOLING AND PROVIDES DIRECT COOLING FOR RX CONTROL ROD LOGIC CASINENTS AND RX TRIP SWITCH 5 EAR. COMPONENTS INVOLVED ARE NON-SAFETY AND NON-SEISMIC.
PURSUANT TO THE ABOVE INFJRMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PR09 ABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTJ OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETf EVALUATION ITEM 10 20 NE-87-JJ31 CMP 35-0479 ADDED A COOLING COIL 10 AUX.8LDG. AIR HANDLING UNIT SGF01 CMP 85-U477 ADDED A COOLING COIL TO AUX. BLDG. AIR HANDLING UNIT SGF01 TO PRO-VIDE COOLING FOR SAFETY-RELATED ECUIPMENT IN PLANT AREA 5 AND THE MAIN STEAM TUNNEL. THE COIL MEETS THE DESIGN CODES AND STANDARDS REQUIRED FOR THE. ORIGINAL AIR HANDLING UNIT. ADDITION OF THE COIL ENHANCES PLANT SAFETY.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTI OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIUUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE br$IS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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10CFRS2.59 ANNUAL REPORT SURMAR8ES e
OF UNION ELECYRIC APPROME9 WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 21 NE-37-J345 OL 1059 REVISED TECH SPEC 5.3.1 TO ALLOW REPLACEMENT OF FUEL RODS WITH FILLERS OL 1059 REVISED TECH SPEC 5.3.1 TO ALLOW REPLACEMENT OF A LIMITED NUMBER OF FUEL RODS WITH FILLER RODS OR VACANCIES BASED ON THE RESULTS OF CYCLE-SPECIFIC RELOAD ANALYSIS. CHANGE PERMITS RECONSTITUTION OF FUEL ASSEMBLIES AND UTILIZA-TION OF THEIR REMAINING ENERGY. THE RELOAD ANALYSIS CNSURES THAT SAFETY CRITER-IAiDESIGN LIMITSiPEAKING FACTORSiAND CORE AVERAGE LINEAR HEAT RATE EFFECTS ARE NOT EXCEEDED. THE RELOAD METHODOLOGY REMAINS UNALTERED AND INCORPORATES AN EXPLICIT MODEL WITH EACH DISCRETE ROD IDENTIFIED. THIS CHANGE WAS APPROVED BY THE HRC IN LICENSE AMENDMENT-24.
PURSUANT TO THE A30VE INF3RMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PR03 ABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORFANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTI OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY
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QUESTIOH DID NOT EXIST.
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REPORT SAFETY EVALUATION ITEM ID 22 NE-37-JJ92 CMP 87-1001 ALLOWED OPTIONAL USE OF ROSEMOUNT TRANSMITTERS IN LEVEL C USES CMP 87-1031 ALLOWED THE OPTIONAL USE OF ROSEMOUNT TRANSMITTERS IN LEVEL C APPLICATIONS. THIS CMP PROVIDED MINOR TECHNICAL CORRECTIONS TO CMP S6-0309 WHICH I
APPLIED TO SAME CHANGE. THE CMP 87-1031 DID NOT CHANGE FUNCTIONAL PERFORMANCE REQUIREMENTS OF THE TRANSMITTERS.
PURSUANT TO THE A80VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE I,
OVER PREVIOUS EVALUATIONS IN.THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY
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QUESTION DID NOT EXIST.
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10CFR50.59 ant 1UAL REPORT SUMMARIES OF UNION ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 23 NE-87-J1J3 RFR NO.3559 REVISED FSAR FIG 13.2-1 YO REFLECT AS-BUILT CONDITION-MA,IN TURBINE RfR NO.3559 REVISED FSAR FIG 10.2-1 TO REFLECT THAT TWO WYE STRAINERS THAT ARE INDICATED SHOULD BE REMOVED FROM THE DRAWING SINCE THEY WERE NEVER INSTALLED.
THE MAIN TUaBINE SYSTEM IS A NONSAFETY-RELATED SYSTEM. THE STRAINERS WERE NO LONGER RE3UIRED WHEN THE MAIN TURBINE WAS CONVERTED FROM PARTIAL ARC TO FULL ARC STEAM ADMISSION.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IAPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTI OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE l
OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTI OR REDUCE THE MAR-I_
GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY CUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 24 N E-67 ' 134 RFR NO.3563 REVISED FSAR FIG 13.4-8 TO SHOW ISO. VALVES CLOSED-S/G BLOWDN TANK J
RFR NO.3560 REVISED FSAR FIG 13.4-S TO SHOW THE ISOLATION VALVES FOR THE STEAM GENERATOR BL0dDOWN FLASH TANK LEVEL GAUGE AS NORMALLY CLOSED. THE GAUGE IS USED FOR LOCAL INDICATION ONLY,AND TANK LEVEL IS SHOWN IN THE A ADWASTE CONTROL ROOM.
ISOLATING THE LEVEL GAUGE FROM SERVICE REDUCES THE NUMBCR OF LEAKS THAT DEVELOP IN THF SIGHT GLASS.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTI OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTI OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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10CFR50.59 ANNUAL REPORT SUMMARIES OF UNION ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS RtPORT SAFETY EVALUATION ITEM ID 25 NE-$7-01Jo MISC.TS DELTA-T ZERO DEFINITION OF DELTA-T ZERO FOR DELTA-T TRIPS IN TECH SPECS MISC.TS DELTA-T ZERO CHANGE REVISED THE FORHULA FOR CALCULATING THE SETPOINT FOR DELTA-T TRIPS. FOR CYCLE 2 THE TECH SPEC VALUE WAS A FIXED VALUE. DURING THE EVALUATION FOR CYCLE 3 IT WAS DETERMINED THAT THE VALUE SHOULD VARY AS A FUNCTION OF THE FULL POWER DELTA-T. THE VALUE THAT VARIES WITH THE FULL POWER DELTA-T IS CONSISTENT WITH OPERATING PRACTISE AND 3AFETY ANALYSIS ASSUMPTIONS.
ALTHOUGH CYCLE 2 TECH SPECS LISTED A FIXED VALUER ACTUAL PLANT IMPLEMENTATION WAS CONSISTENT WITH THE C Y C I.E 1 METHODOLOGf AND DID NOT VIOLATE TECH SPECS. THE CYCLE 2 DELTA-T ZER0 WAS ADJUSTED FOR EACH LOOP SO THAT THE DELTA-T INDICATORS SHOWED 100% AT FULL POWER i AND INDIVIDUAL LOOP DELTA-T VARIATION WAS LIMITED IN PRACTISE TO 2.61% WHICH JAS WITHIN THE 4.5% MARGIN EXISTING DUE TO THE DIF-FEREhCE SETWEEN THE LICENSED CORE THERMAL POWER (3411MJT) AND THE ANALYZED THER-MAL POWER (3565MWT).
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIdILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
I REPORT SAFETY EVALUATION ITEM ID I
26 NE-o7-4113 RFR NO.3672 CORRECTED ERROR IN FSAR TABLE 3.11(B) (SHEET 29) FOR RCS COMPONENT RFR NO.3672 CORRECTED DESIGNATION ERROR IN FSAR T ABLE 3.11(B)(SHEET 29) FOR
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RCS COMPONENTS BS-TE-XXXX WHICH SHOULD SE BB-T/C-XXXX TO AGREE WITH OTHER DESIGN DOCU1ENTS AND FIELD INSTALLATION. THIS IS A TYPOGRAPHICAL CHANGE ONLY.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROSASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIOENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
I THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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10CFR50.59 ANMUAL REPORT SUMMARIES OF UNIOM ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 27 NE-67-J273 RFR NO.2d43 REVISED FSAR SECT 6.3.5 AND FIG 6.3-1 TO DELETE BORON INJ. ALARMS RFR No.2840 REVISED FSAR SECTION 6.3.5 AND FIGURE 6.3-1 TO DELETE HIGH AND LOW ALARMS FOR THE BORON INJECTION SURGE TANK FROM THE CONTROL BOARD ANNUNICIATOR.
THESE WERE DETERMINED TO BE UNNEEDED CONTROL ROOM ALARMS,SINCE HEAT TRACING THE BOPON INJECTION TANK IS NOT REQUIRED; FLUID RECIRCULATION THROUGH THE BORON IN-JECTION SURGE TANK IS NOT REQUIRED; AND AN UNALARMED ABNORMAL LEVEL IN THE BIST WOULD NOT ADVERSELY EFFECT THE SAFETY-RELATED INJECTION FLOWPATH THROUGH THE BIT.
PURSUANT F0 THE ASOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DF. FINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY CUESTION DID NOT EXIST.
r REPORT SAFETY EVALUATION ITEM ID 25 NE-87-4275 RFR NO.3231 CORRECTED FSAR FIG 10.4-6 TO AGREE WITH VENDOR DWG FOR AE-FV-00018, RFR NO.323* CORRECTED FSAR FIG 10.4-6 TO AGREE WITH VENDOR DRAWING FOR FEEDWATER SYSTEM VALVES AE-FV-30318 AND AE-FV-03J28. THE FIGURE SHOULD SHOW THESE VALVES AS FAILING 'AS IS'(NEITHER OPEN OR CLOSED). THIS CHANGE INVOLVED DOCUMENTATION ONLY.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT 09 MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-
_ GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFE 1Y QUESTION DID NOT EXIST.
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OF UNION ELECVRIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 29 NE-87-0277 RFR NO.3513 LOCKED OPEN FIRE PROTECTION BYPASS VALVES (KC-XV-0261/2)AT POWER RFR NO.3513 LOCKED OFEN FIRE PROTECTION BYPASS VALVES,KC-XV0261 AND KC-XV3262
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DURING POWER OPERATIONS SO THAT AN ELECTRICAL FAILURE TO SOLENOID CIRCUITRY FOR SPRINKLER ACTUATION VALVES COULD NOT CAUSE THE SYSTEM TO BE DECLARED INOPERABLE. THE CHANGE DOES NOT ALTER THE FUNCTION OF THE SYSTEM AND ORIGINAL DESIGN BASES ARE MET. FSAR FIG ?.5.1-1 IS REVISED.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEGUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-I.
GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 30 NE-87-0273 RFR NO.3766 REVISED FSAR FIG 11.2-1 To SHOW AS-9UILT FOR LIO.RADWASTE SYS. VALVE RFR NO.3766 REVISED FSAR FIG 11.2-1 TO SHOW THE AS-8UILT CONFIGURATION OF THE VALVE PACKING LEAK-OFF HEADER. THE LEAK-OFF TUBING CONTROLS CONTAMINATION IN THE EVENT OF VALVE PACKING LEAKAGE. CHANGE TO THE FIGURE SHOWS VARIOUS POINTS OF ENTRY INTO THE HEADER. THE CHANGE IS FOR DOCUMENTATION ONLY.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE 8 ASIS FOR ANY TECHNICAL SPECIFICATION.
I THE EVALUATION DETERMINED THAT AN UNREVIEVED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 31 NE-87-J345 CN 455 SA 10.2.2.3.2 REVISED TO GIVE RANGE OF VALUES FOR OVERSPEED TRIP-TURBINE CN 455 SA 1J.2.2.3.2 WAS REVISED TO GIVE THE MANUFACTURER'S ACCEPTABLE RANGE OF VALUES FOR TUR9INE OVERSPEED AND BACKUP OVERSPEED TRIPS. THE CHANGE ADDS "A NOMINAL" TO DESCRIPTION OF ACTUAL TRIP SETTINGS.
PURSUANT TO THE A90VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROSA9ILITY OF OCCURFNCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP--
MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
I THE EVALUATION DETERMINED THAT nN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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I 19CFR50.59 ANNUAL REPORT SUMMARIES OF UNION ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS REPORI SAFETY EVALUATION ITEM ID 32 NE-87-e04d OL 1953 REVISED TS 3/4.7.5 TO BE CONSISTENT WITH FSAR CONDITIONS FOR UHS OL 1253 REVISED TS 3/4.7.5 TO REFLECT EXISTING CONDITIONS FOR THE ULTIM ATE HEAT SINK AS DESCRIBED IN THE FSAR. CHANGES TO THE LCO AND ACTION STATEMENT ARE DONE FOR CLARITY ONLY TO DELINEATE THE FACT THAT THERE ARE TWO SEPARATE TRAINS OF COOLING AVAILABLE FOR THE ESSENTIAL SERVICE WATER SfSTEM. NO CHANGES ARE BEING MADE TO SYSTEM OR ITS FUNCTIONS. CHANGES WERE APPROVED BY THE NRC IN LI-CENSE AMENDMENT-25.
PURSUANT TO THE ABOVE INFORMATION, THE CHA4GE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; 0% CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE*0RT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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REPORT SAFETY EV3LUATION ITEM ID 33 NE-87-oJ4=
OL 1048 REVISED TS TABLE 3.3-3 YO CLARIFY BLOCKING OF AUX.FEEDWATER START SIGNA OL 1048 REVISED TECH SPEC TABLE 3.3-3 TO CLARIFY 8 LOCKING OF AUXILIARY FEEDWATER 1
START SIGNALS DURING NORMAL PLANT STARTUPS AND SHUTDOWNS. A NOTE TO THE T ABLE
. ALLOWS BLOCKING THE SIGNAL JUST BEFORE SHUTDOWN OF THE LAST OPERATING MAIN FEEDWATER PUMP DURING PLANT SHUTDOWN AND REQUIRES SIGNAL RESTORATION JUST AFTER THE FIRST HAIN FEEDWATER PUMP IS PLACED INTO SERVICE DURING STARTUP. CLARIFICA-TION DOES NOT CHANGE FSAR NOR SER EVALUATIONS. THE CHANGE WAS APPROVID BY THE NRC IN LICENSE AMENDMENT-26.
I PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE S AFE TY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
.THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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10CFR50.59 ANNUAL REPORT SUMMARId5 0F UNION ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 34 NE-57-2J53 CMP 67-1036 INSTALLED A BLOWDOWN SILENCER AND 8 INCH TEE IN CNTMT PURGE SYSTEM C,tP 67-1336 INSTALLED A BLOWDOWN SILENCER AND 8 INCH TEE IN THE CONTAINMENT PURGE SYSTEM. MODIFICATION FACILITATES AN ILRT DEPRESSURIZATION. DURING NORMAL OPERATION OF THE CONTAINMENT PURGE SYSTEM THE SILENCER IS NOT CONNECTED TO ANY SYSTEMS AND THE DUC" ACCESS HATCH IS dLANKED OFF, ALLOWING NO POSSIBILITY OF CREATING A FUNCTIONAL (SYSTEM LINE-UP)PR0dLEM. THE DESIGN DOES NOT CH ANGE THE FUNCTION OF THE SYSTEMS INVOLVED EXCEPT DURING AN ILRT OUTAGE. THE ONLY POSSIBLE FAILURE WOULD RESULT FROM A SEISMIC EVENT. THE EQUIPMENT HOWEVER IS DESIGNED TO SEISMIC CRITERIA.
PJRSUANT TO THE A30VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF ?CCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO 5AFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
r REPORT SAFETY EVALUATION ITEM ID 35 NE-67-4125 RCA RP 87-023 EVALUATED PROCEDURE FOR ' DEWATERING' PROCESS FOR WET WASTES RCA RP 87-J28 EVALUATED THE 'DEJATERING' PROCESS USED BY AN OUTSIDE VENDOR TO PROCESS CALLAWAY WET WASTE. THE USE OF THE BULK WASTE DISPOSAL STATION DIDN'T INVOLVE AN UNREVIEWED SAFETY QUESTION SINCE THE WORST POSSISLE ACCIDENT WOULD INVOLVE THE RELEASE OF THE PRIMARY SPENT RESIN TANK INSIDE THE RADWASTE 9LDG.
THROUGH THE BULK WASTE TRANSFER SYSTEM AND THIS RELEASE WOULD SE CONTAINED BY THE RADWASTE TREATMENT SYSTEMS AND IS BOUNDED BY FSAR ANALYSES.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTI OR REDUCE THE MAR-GIN OF. SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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i 1GCFR50.59 ANNUAL REPORT SUMMARIES OF UNION ELECTRIC APPROUED WRITTEN SAFETY EVALUATIONS l
l REPORT SAFETY EVALUATION ITEM IO 36 NE-ST-0267 RFR N O. 3 9 41 EVALUATED NEED TO ADD CAUTION STATEMENT TO EMERGENCY OPE, RATING PROC RFR NO.3941 REQUIRED THE ADDITION OF A CAUTION STATEMENT TO EMERGENCY OPERATING PROCEDURES,EOPS, TO ALERT OPERATORS 06 POTENTIALLY INACCURATE INSTRUMENT READING (PRESSURE TdANSMITTERS IN THE STEAM TUNNEL) AFTER A STEAMLINE BREAK IN THE STEAM TUNNEL (AREA 5). AN EVALUATION OF THE EFFECTS OF STEAM SUPERHEATING FOLLOWING A POSTULATED STE AM LINE BRE AK OUTSIDE CONT AINMENT,LE AD TO NEW PRESSURE AND TEMP-ERATURE PROFILES FOR CLASS 1E EQUIPMENT IN THE STEAM TUNNEL AND THE FACT THAT PRESSURE TRANSMITTERS EXCEED THEIR QUALIFIED TEMPERATURE WELL AFTER THEY GENER-ATE A STEAM LINE ISOLATION SIGNAL. THEREFORE IN THE POST-ACCIDENT CONDITION ALTERNATE INSTRUMENTATION SHOULD BE USED SY THE OPERATORS. THE ALTERNATE DE-VICES ARE CLASS 1E AND ARE QUALIFIED.
THE STEAMLINE BREAK IN AREA 5 WAS AP-PROV2D 9Y THE NRC IN A LETTER DATED FE3RUARY 18,1988.
PURSUANT TO THE ASOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PR09 ABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
^
REPORT SAFETY EVALUATION ITEM ID 37 NE-37-J268 RFR NO.3998 CORRECTED FSAR FIG 9.2-5 FOR DUPLICATE VALVE NOS. ON DIFF. VALVES RFR NO.3998 CORRECTED FSAR FIG 9.2-5 FOR DUPLICATE VALVE ID NUMBERS ASSIGNED TO DIFFERENT VALVES. THE COMPONENTS INVOLVED WERE PDTABLE WATER SYSTEM VALVES AND A NEW VALVE NUMBER WAS ISSUED FOR ONE. THIS CHANGE WAS FOR DOCUMENTATION ONLY.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
e 9
10CFR50059 ANNdAL REPORT SUMMARIES s
OF UNION ELECYRIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 38 NE-d7-0269 RFR NO.3936 CORRECTED FSAR FIG 9.2-4 TO SHOW AS-BUILT CONFIGURATION,WITH 2 VALV RFR NO.3986 CORRECTED FSAR FIG 9.2-4 To SHOW THE AS-BUILT CONFIGURATION WITH TWO VALVES LEFT IN PLACE ON THE DEMIN. DEGASIFIER PACKAGE. THE VALVES ARE LO-CATED ON THE DRAIN PIPING OF THE VACUUM PUMPS. THE VALVES DO NOT AFFECT OPERA-TION OF THE VACUUM PUMPS OR THE DEGASIFIER SKID. THIS IS NONSAFETY-RELATED SYSTEM.
PURSUANT TO THE A30VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCbRENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTJ OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVE0 PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE 6 ASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 39 NE-67-0274 RFR No.3131 REVISED FSAR FIG 9.5.6-1 TO SHOW AS-BUILT CONFIGURATION,D/G SYSTEM RFR h0.3131 REVISED FSAR FIG 9.5.6-1 TO SHOW THE AS-BUILT CONFIGURATION OF THE SUPPLY LINES TO THE EMERGENCY DIESEL GENERATOR SHUTDOWN SOLENOID VALVE AIR TANK.
IN AS-BUILT CONDITION THE NORMAL SUPPLY TO THE AIR TANK IS FROM STARTING AIR TANK 8.
THIS CHANGE DOES NOT AFFECT THE OPERATION OF THE DIESEL GENERATOR.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-
~
MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTJ OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED'IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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13CFR50.39 ANNUAL REPORT SUMMARHES OF UNION ELECTRIC APPROUED WRITTEN SAFETY EVALUATIONS e
REPORT SAFETY EVALUATION ITEM ID 40 NE-87-J339 MISC WEST.SCP-87-212 EVALUATED C ALLAW AY 10RBINE TRIP WITH FAILURE /F$ST PWR TRNF MISC WEST.SCP-97-212, WESTINGHOUSE LETTER SCP-87-212, DATED JULY 9,1987 9AISED THE CONCERN THAT THE CALLAWAY TURBINE T4IP WITH FAILURE OF FAST POWER TRAFL/ER ACCI-DENT SCENARIO,THE NOST LIMITING CONDITION II EVENT WITH RESPECT TO PEAK PRES-SURE,WOULD RESULT In A CONDITION WHERE DN8R MAY NOT BE MET. THIS ACCIDENT SCEN-ARIO IS NOT INCLUDED IN FSAR ANALYSES,80T WAS DETERMINED TO BE $0UNDED SY FSAR ANALYSES. ADDITIONAL STUDIES FOR THE RESULTING LOSS OF FLOW TRANSIENT CONFIRM THAT NO FUEL DAMAGE OCCURS AND OFFSITE DOSE LIMITS ARE MAINTAINED. WHEN REACTOR TRIP ON TUR9INE TRIP IS AVAILABLE,A. TURBINE TRIP WOULD CAUSE AN IMMEDIATE REAC-TOR TRIP AND NO NEW SCENARIO IS C1EATED,AND FSAR DNS ANALYSES REMAIN BOUNDING.
THE NEW-SCENARIO IS NOT CREDIBLE AT CALLAWAY DUE TO THE DESIGN OF THE REACTOR TRIP ON TURdINE TRIP.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PR39 ABILITY OF OCCURENCE OR CONSEQUENCES OF AF ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY GUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 41 NE-36-J203 CMP 84-063$ REPLACED DETECTORS WITH PHYSICAL 9ARRIERS CMP 84-0636 REPLACED OREAKWIRE DETECTORS WITH PHYSICAL BARRIERS. CHANGE DID NOT INVOLVE ANY SAFETY-RELATED EQUIPMENT.
PURSUANT F0 THE AB0VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PR08A81 LIT ( OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVA'.UATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EYIST.
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10CFR50.59 ANMUAL REPORT SUMMQRIES OF UNION ELECTRIC APPROBED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 42 NE-37-4J1o CMP d5-2371 INSTALLED LOCAL COMTROL AND REMOVED SEALING CIRCUIT FOR, VALVE CMP 85-0371 INSIALLED LOCAL CONTROL AND REMOVED THE SEALING CIRCU1T FOR THE CONDENSATE POLISHER BYPASS VALVE AD-HV-28. CHANGES ALLOW THE VALVE TO BE CON-r TROLLED FROM THE TANEL AK182 AS A THROTTLE VALVE WHEN PARTIAL FLOW IS DESIRED THROUGH THE CONDENSATE POLISHERS. THE VALVE SERVES NO SAFETY FUNCTION AND HAS NO SAFETY DESIGN BASIS.
PURSUANT TO THE ABOVE I N F O RM AT ION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PR09 ABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CRfATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE DVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETT AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 43 NE-37-0257 RFR NO.4J37 UPDATED FSAR FIG.9.4-6 TO REFLECT ADDED CONTROL SWITCHES (AS-BUILT)
RFR NO.4207 UPDATED FSAR FIG.9.4-6 TO REFLECT AS-BUILT CONDITIONS WHERE EIGHT LOCAL CONTROL SWITCHES WERE ADDED TO THE HYDROGEN MIXING FANS AND THE CONTAIN-I MENT COOLER FANS IN THE EVENT OF A CONTROL ROOM FIRE. COMPONENT FUNCTIONS RE-MAIN UNALTERED.
PURSUANT TO THE ASOVE INFORMATIONr THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROSABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE
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OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE 8 ASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEVED SAFETY 1
QUESTION OID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 44 NE-87-J261 RFR NO.3997 REVISED FSAR FIG 1J.4-12 TO DELETE DUPLICATE NON-Q VALVE NUMBERS RFR NO.3997 REVISED FSAR FIG 10.4-12 TO DELETE DUPLICATE VALVE NUMBERS AND RE-ASSIGN ANOTHER VALVE NUMBER FOR NONSAFETY-RELATED VALVES IN THE SECONDARY WASTE SYSTEM.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAf2TY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
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THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
I
10CFR50.59 ANEUAL REPORT SUMMARIES L
OF UMION ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION L
ITEM ID 45 NE-37-J262 RFR NO.411J EVALUATED SEISMIC II/I CONCERNS FOR EQUIP. STORED IN A U X,.
BLDG RFR NO.4118 EVALUATED SEISMIC II/I CONCERNS FOR NON-PLANT EQUIPMENT STORED IN VARIOUS LOCATIONS IN THE AUXILIARY BLDG. THE EVALUATION VERIFIED THAT STORAGE AREAS ARE NOT NEAR SAFETY-RELATED EQUIPMENT AND SEISMIC II/I CONCERNS HAVE NO IMPACT.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 46 NE-87-4263 RFR NO.4116 REVISED FSAR FIG 2.5-527 FOR AS-BUILT CONDITIONS FOR SETTLE. MON.PLA RFR NO.4116 REVISED FSAR FIG 2.5-307 FOR ACTUAt FIELD CONDITIONS FOR SETTLEMENT MONITORING PLATES,SMP. THE REVISIONS DO NOT DEGRADE THE SETTLEMENT MONITORING PROGRAM.
PURSunNT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBA8ILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 47 NE-37-0264 RFR NO.4100 REV"SED FSAR FIG 9.5.6-1 TO SHOW D/G SYSTEM VALVE NORMALLY OPEN RFR NO.4100 REVISED FSAR FIG 9.5.6-1 TO SHOW THE DIESEL GENERATORS AIR START COMPRESSORS CROSS CONNCCT ISOLATION VALVE NORMALLY OPEN VERSUS LOCKED CLOSED.
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SINCE EMERGENCY SHUTDOWN IS NOT A SAFETY FUNCTION THE VALVE POSITION (OPENED OR CLOSED)DOES NOT AFFECT OPERASILITY.
PURSUANT TO THE ABOVE INFORMATION, TH E CH ANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIF-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY I
-QUESTION DID NOT EXIST.
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10CFR50.39 ANNUAL REPORT SUMMARIES OF UNION ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 48 NE-37-J265 RFR NO.3971 REVISED FSAR FIG 5.1-1 TO SHOW NEW NUMBER FOR AN EXISTIt{G COMPONENT RFR NO.3971 REVISED FSAR FIG 5.1-1 TO SHOW 4 NEW COMPONENT NUMBER FOR AN EXIST-ING COMPONENT IN THE REACTOR COOLANT SYSTEM. THE COMPONENT AND NEW DESIGNATION ARE VALVE 33-V-0420. THE CHANGE ONLY INVOLVES A DRAWING REVISION,DUE TO AN ER-ROR OF ASSIGNIreG DUPLIC ATE DESIGNATORS FOR TWO DIFFERENT VALVES.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THi SASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITFM ID 49 NE-37-J271 RFR NO.1865 CREATED FSAR FIG 13.3-1,SHT 4,45 COMPOSITE OF OTHER FSAR FIGURES RFR NO.1863 CREATED FSAR FIG 10.3-1,$HEET 4,45 A COMPOSITE OF OTHER FSAR FIG-URES. THE NEW FIGURE SHOWS ALL THE INTERCONNECTED MAIN STEAM SYSTEM TO THE SECONDARY SIDE OF STEAM GENERATOR A ON ONE FIGURE. INFORMATION FOR STEAM GEN-ERATORS 8,C,0 CAN BE CROSS REFERENCED FROM TA3LES. THIS INVOLVED A DOCUMENTA-TION CHANGE ONLY.
PURSUANT TO THE ABOVE *NFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE,IN PROBABILITY OF OCCURENCs OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EGUIP-MENT IMPORTANT TO SAFETY 7VER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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10CFR53.59 ANNUAL mEPORT SUGMARIES OF UNION ELECTRIC APPROUED 2
WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 50 NE-87-0298 ETP-KB-ST2J2rREV 0 PROCEDURE DEVELOPED TO TEST SREATHING AIS SYSTEM, ETP-KB-ST202rREV 0 PROCEDURE WAS DEVELOPED TO OPERATIONAL TEST THE SREATHING AIR SYSTEM.
THIS TEST WAS REQUIRED PRIOR TO DECLARING THE SYSTEM OPERATIONAL. THIS SYSTEM HAS NO SAFETY-RELATED FUNCTION. THE ONLY SAFETY COMPONENTS IN THE SYSTEMr THE CONTAINMENT ISOLATION VALVESr ARE NOT TESTED IN THE SCOPE OF THIS PROCEDURE.
PURSUANT TO THE A30VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PR0043ILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RcPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM 13 51 NE-87-3346 CN 465 SP 5.4.7.2r9.1 REVISED FSAR DESCRIPTION OF RHR SYSTEM DURING REFUELING CN 465 SP 5.4.7.2 AND 9.1.4.2.3.1 WERE REVISED FOR PROCEDURES OF RHR OPERATION DURING REFUELING. CHANGE AFFECTS MANNER OF TRANSFER OF 90 RATED REFUELING WATER BETWEEN THE REFUELING WATER STORAGE TANK AND THE REFUELING CAVITY. SYSTEM FUNC-TIONS ARE NJT ALTERED AND SAFETY DESIGN BASES ARE UNAFFECTED.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION Of EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTi OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNrEVIEWED SAFETY QUESTION DID NOT EXIST.
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10CFR50.59 ANNUAL REPORT SUMMAR2ES OF UNION ELECTRIC APPROVED l
WRITTEN SAFETY EVALUATIONS
[
l l
REPORT SAFETY EVALUATION ITEM ID 52 NE-37-234d RFR No.3824 REVISED FSAR SP TABLE 7A-3 DOCUMENTATION FOR EQUIPMENT U,PGRADE RFR NO.3824 REVISED FSAR SP TABLE 7A-3 TO UPDATE DOCUMENTATION FOR EQUIPMENT ENHANCEMENTS OUTSIDE OF THE CALLAWAY EQUIPMENT QUALIFICATION PROGRAM.
ALL ITT VENDOR ACTUATORS ARE BEING UPGRADED BY RETURNING THEM TO ITT FOR REFURBISH-MENT. THE UPGRADING INCLUDES SEAL REPLACEMENT FROM POLYURETHANE TO VITON AND SPRING REPLACEMENT ON SOME ACTUATORS. THE CHANGES RESULT IN PEVISED PART NUM-L BERS AND MAINTENANCE REQUIREMENTS. THESE CHANGES DO NOT ALTER PLANT SAFETY.
PUR$UANT TO THE ASOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN I
PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR. CREATE POSSISILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY GUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 53 NE-37-J346 OL 1051 REVISED TS 3.4.8 AND 6.9.1.5 FOR REPORTING IODINE SPIKING OL 1251 REVISED TS 3.4.8 ACTION STATEMENT AND BASES,AND TS 6.9.1.5 FOR REQUIRE-MENTS FOR REPORTING IODINE SPIKING AND FOR SHUTTING DOWN THE PLANT AFTER 800 HRS OF OPERATION WITH A DOSE EQUIVALENT I-131 VALUE OF 1 MICR0 CURIE /GM OR
. GREATER. CHANGES ARE CONSISTENT WITH THE GUIDANCE GIVEN IN GENERIC LETTER 85-19, AND WERE APPROVED BY THE NRC IN LICENSE AMENDMENT-27.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBA9ILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR M ALFUNCTIO!J OF EQUIP-I MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE 0VER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEVED SAFETY QUESTION DID NOT EXIST.
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P 10CFR50.59 ANNUAL REPORT SUMMARIES OF UNION ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 54 NE-87-JJ99 CMP 87-1343 SPLICED WIRES FOR LIMIT SWITCHES ON SAFETY-RELATED VALVES CMP 87-1043 INSTALLED SPLICES IN VALVE TERMINAL 90XES FOR VALVE STEM MOUNTED LIMIT SWITCHES AND VALVE SOLENOIDS FOR THE FOLLOWING VALVES: BB-HV-5702A;-
EJ-HV-8701a;38-PCV-455A;88-PCV-456A;68-HV-8310A,0,C AND EP-HV-8808A,8,C,0. THE CHANGE REPLACED TERMINAL BLOCKS OF QUESTIONABLE QUALIFICATION. THE ENVIRJN-MENTALLY QUALIFIED SPLICE KITS ASSURE OPERABILITY OF THE VALVES FOR NORMAL AND ACCIDENT CONDITIONS.
PURSUANT TO THE ASOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN 7HE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY i/ALUATION ITEM ID 55 NE-37-J251 ETP-HC-ST031,REV O PROCEDURE DESCRIBED ALTERNATE PUMP CONFIGURATION FOR PHC06 ETP-HC-ST001,REV D PROCEDURE DESCRIBED THE TEMPORARY SET-UP AND OPERATION OF AN ALTERNATE PUMP CONFIGURATION FOR PHCJ6,THE SECONDARY EVAPORATOR BOTTOMS PUMP.
THE PROCEDURE MONITORED THE ALTERNATE PUMP FOR LEAKAGE AND IMPACT ON THE METER-ING PUMP FOR DRUMMING. THE WORST ACCIDENT SCENARIO POSSIBLE WHILE PERFORMING THE PROCEDU4E WOULD BE A BROKEN LINE FROM THE SECONDARY EVAPORATORS BOTTOM TANK AND TANK DISCHARGE. FLOOR AND EQUIPMENT DRAINS dOULD C03TAIN LIQUID RELEASES AND THE RADWASTE HVAC SYSTEM WOULD CONTAIN ANY GASEQUS RELEASES. ADMINISTRATIVE
[
CONTROLS MINIMIZE ACCESS TO THIS ROOM. THIS IS NOT A SAFETY-RELATED SYSTEM.
PURSUANT TO THE A30VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBAaILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT! OR CREATE POSSIBILITY FOR ACCIDENT OR M4LFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTI OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE OASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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19CFR50059 ANNUAL REPORT SUMM ARIES
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OF UWION ELECTR7C APPRuoED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 56 NE-37-J27d RFR NO.1247 REVISED FSAR FIG 13.2-1 FOR AS-9UILT RX TRIP ON TURBINE, TRIP PFR No.1247 REVISED FSAR FIG 1J.2-1 FOR THE AS-BUILT DESIGN OF THE REACTOR TRIP ON A TURBINE TRIPUNTICIPATORY FROM EMERGENCY TRIP FLUID PRESSURE LOW SWITCHES).
THIS CHANGE ONLY REVISES DOCUMENTS.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF CCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 57 NE-87-0272 RFR NO.2440 INCREASED MAXIMUM ALLOWABLE STROKE TIMES FOR VARIOUS VALVES RFR NO.244; INCREASED MAXIMUM ALLOWABLE STROKE TIMES FOR VARIOUS ALrBBrBGrBNr EFrAND EG Sf8TEMS VALVES. THE INCREASE GAVE RELIEF TO ASME XI VALVE TESTING.
EFFECTS ON SYSTEM PERFORMANCE WERE REVIEWED AND DETERMINED NOT T3 BE ADVERSE.
THE VARIOUS SYSTEMS ARE ABLE TO PERFORM DESIGN FUNCTIONS AND ARE NOT COMPROMISED SY SMALL INCRE ASES IN STROKE TIME.
PURSUANT TO THE A90VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 58 NE-37-2276 RFR No.3501 CORRECTED A DRAFTING ERROR ON FSAR FIG 9.5.6-1 FOR VALVE ID RFR NO.3501 CORRECTED A DRAFTING ERROR ON FSAR FIG 9.5.6-1 TO GIVE THE CORRECT VALVE ID NUMBER FOR THE STAND 3Y DIESEL ENGINE SYSTEM VALVE KJ-V0735A. THE CHANGE INVOLVED DOCUMENTATION ONLY.
PURSUANT TO THE ABOVE INFORMATIONr THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-NENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT. TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.-
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
1JCFR50.59 ANNUAL REPORT SUMMARIES OF UNION ELECTRZC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION c
ITEM ID i
59 NE-67-J236 CMP 87-1034 REDUCED ANTI-SIPHON HOLES ON FUEL POOL SKIMMER LINES 1
CMP 87-1054 REDUCED ANTI-SIPHON HOLES ON THE FUEL POOL SKIMMER LINES TO IMPROVE THE EFFICIENCY OF THE SURFACE SKIMMERS SINCE PERFORMANCE SHOWED THAT THE HOLES ALLOW DEBRIS TO BYPASS THE SKIMMER STRAINER SASKET. CALCULATIONS VERIFIED THAT THE REDUCED SIPHON HCLE WILL STILL BREAK ANY POTENTIAL SIPHON ACTION AND THE REDUCED HOLE SIZE IS STILL LARGE ENOUGH NOT TO SE OLOCKED BY DESRIS. THE CHANGE DOES NOT AFFECT OPERATION OF SAFETY-RELATED EQUIPMENT OR INSTRUMENTATION WHILE IT DOES IMPROVE OPTICAL CLARITY AND THE EFFECTIVENESS OF REMOVING FLOATING DEBRIS. THE CHANGE REVISED SEVERAL FSAR P& IDS.
PURSUANT TO THE A30VE INF ORM ATION, THE CHANGE DOES NOT INVOLVE AN INCREA3E IN L
PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-l PORT; OR C9EATE POSSIBILITY FOR ACCIDEMT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID
$2 NE-87-0292 ETP-EM-STJJ4,REV 0 PROCEDURE 03TAINED TEST DATA ON BIT ISOLATION VALVES ETP-EM-ST204,REV 0 PROCEDURE OaTAINED TEST DATA ON THE BORON INJECTION TANK ISOLATION VALVES WHEN STROKED UNDER DIFFERENTIAL PRESSURE CONDITIONS. THIS TEST COMPLIES JITH I.E. BULLETIN 85-23. DURING THE PROCEDUEE THE PRESSURES, i
TEMPERATURES AND FLOWS ARE MAINTAINED BELOW EQUIPMENT DESIGN LIMITS. CONCERNS 0F RCS/ REFUELING POOL INVENTORY CONTROL ARE ELIMINATED BY USING THE RHR DIS-CHARGE AS A SUCTION SOURCE FOR THE CENTRIFUGAL CHARGE PUMP. MARGINS OF SAFETY ARE NOT DECREASED.
PURSUANT TO THE A90VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PR09A91LITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-l GIN OF SAFETY AS DEFINED IN THE SASIS FOR ANY TECHNICAL SPECIFICATION.
l THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY l
QUESTION DID NOT EXIST.
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10CFR50059 ANNUAL REPORT SUMMQRIES OF UNION ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS P
REPORT SAFETY EVALUATION ITEM ID 61 NE-57-J291 ETP-BG-ST036,REV 2 PROCEDURE REVISED DIFF. PRESSURE TEST OF CVCS VALVES ETP-BG-ST006,REV 2 PROCEDURE REVISED DIFFERENTIAL PRESSURE TESTING OF CVCS VALVES. CHANGE REVISED A PREREQUISITE FOR REFUELING WATER STORAGE TANK LEVEL TO 3E GREATER THAN OR ECUAL TO 16% TO A REQUIREMENT FOR GREATER THAM OR EQUAL TO 12%. THE IMPLEMENTATION OF THE PROCEDURE DOES NOT AFFECT RWST LEVEL. THE NEW LEVEL REQUI4EMENT STILL MEETS TECH. SPEC. WHILE PROVIDING GREATER FLEXIBILTY IN IMPLEMENTATION OF THE PROCEDURE.
PURSUANT TO THE ABOV. INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 02 NE-S7-3272 ETP-BG-ST236,REV 3 PROCEDURE REVISED DIFF. PRESSURE TEST OF CVCS VALVES ETP-9G-ST036,REV 3 PROCEDURE REVISED DIFFERENTIAL PRESSURE TESTING OF CVCS VALVES SY ADDING A STEP TO CLOSE CERTAIN VALVES DURING TEST PERFORMANCE. FLOW THROUGH THESE VALVES MUST BE ISOLATED IN ORDER TO OBTAIN THE REQUIRED TEST PRESSURE. THE VALVES TO BE CLOSED ARE THE CONTAINMENT ISOLATION / SEAL INJECTION ISOLATION VALVES BG-HV-8351A,B,C,D. THLSE VALVES ALLOW FILTERED SEAL INJECTION WATER TO THE REACTOR COOLANT PUMP SEALS. ISOLATED SEAL INJECTION IS ACCEPTABLE DURING PERFORMANCE OF THE TEST AND PROVIDED THERE ARE NO REFUELING. POOL LEVEL CHANGES DURING THE TEST.
PURSUANT TO THE aBOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PR09 ABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMFORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SArETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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70CFR50.59 ANNUAL REPORT SUMMARIES OF UEION ELECTRIC SPPROVED l
WRITTEN SAFETY EVALUATZONS REPORT SAFETY EVALUATION ITEM ID 63 NE-87-0293 ETP-BG-ST036,REV 0 PROCEDURE DEVELOPED TO DIFF. PRESSURE TEST CVCS VALVES ETP-8G-ST206,REV 0 PROCEDURE WAS DEVELOPED TO DIFFERENTIAL PRESSURE TEST CVCS VALVES. THE TEST COMPLIES WITH NRC I.E. NOTICE 85-03. THE TEST USES RHR LETDOWN FLOW THROUGH CVCS. THE TEST VALVES ARE OPENED AND CLOSED UNDER NORMAL FLOW CONDITIONS AND ARE STROKED OPEN OR CLOSED AS THEY WOULD RESPOND NORMALLY TO A SI SIGNAL.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PR05 ABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 64 NE-d7-0294 ETP-ZZ-31313,REV 1 PROCEDURE REVISED S/G PRIMARY N3ZZLE DAM INSTALL./ REMOVAL ETP-ZZ-01310,REV 1 PROCEDURE REVISED S/G PRIMARY N0ZILE DAM INSTALLATION / REMOVAL SY UTILIZING A NEW MATERIAL GASKET SEAL WHICH REQUIRES NEW TORQUE VALUES.
THE NEW GASKET IMPROVED LEAKAGE PREVENTION.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY CUESTION DID NOT EXIST.
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10CFR52.59 ANNUAL REPORT SUMMARIES OF UN80N ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM IJ 65 NE-$7-J295 ETP-FC-ST001,REV 0 PROCEDURE DEVELOPED TO DIFF. PRESSURE TEST AUX. FEED. VALVE ETP-FC-ST021rREV 0 PROCEDURE WAS DEVELOPED TO DIFFERENTIAL PRESSURE TEST THE AUXILIARY FEEDWATEP PUMP TURBINE TRIP / THROTTLE VALVE ITS DESIGN CONDITIONS.
TEST PROCEDURE PRESSURES, TEMPERATURES,AND FL0dS 00 NOT CAUSE EQUIPMENT EXPOSURE BEYOND DESIGN LIMITS. TEST COULD PLACE PLANT IN A TECH. SPEC. ACTION STATEMENT TO RESTORE AN INOPERABLE PUMP OR TRAIN. PERFORMANCE OF THE TEST WOULD NOT EXCEED TECH. SPEC. ACTTON STATEMENT LIMITATIONS.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTJ OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTI OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT ExaST.
REPORT SAFETY EVALUATION ITEM 13 66 NE-S7-D296 ETP-EM-ST0J3,REV 0 PROCEDURE DEVELOPED TO DIFF. PRESSURE TEST SI SYSTEM VALVES ETP-EM-ST003,REV 0 PROCEDURE WAS DEVELOPED TO DIFFERENTIAL PRES $URE TEST SAFETY INJECTION SYSTEM MOTOR OPERATED VALVES. THE TEST COMPLIES WITH NRC IE 8ULLETIN 85-33. DURING TEST PERFORMANCE PRESSURESrTEMPERATHRE$ RAND FLOWS DO NOT EXCEED EQUIPMENT DESIGN LIMITS. TEST PREREQUISITES ENSURE THAT TECH SPECS ARE NOT VIOLATED IN MODE SIX. TECH SPEC ACTION STATEMENTS ARE NOT ENTERED.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTJ OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED TH AT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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10CFR50.59 AWNUAL REPORT SUMMARIES OF UNION ELECTRIC APPROMED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM 10 67 NE-87-J297 ETP-SR-00020,REV 7 PROCEDURE REVISION FOR FLUX AND THERMOCOUPLE MAPP,ING ETP-SR-J3020,REV 7 PROCEDURE REVISION ALLOWS TEMPORARY 90DIFICATION TO THE FLUX MAPPING CONSOLE IN THE EVENT OF A WITHDRAW LIMIT SWITCH FAILURE. CHANGE ALLOWS CORRECT INDICATION OF A WITHDRAJN DETECTOR,WHILE REMOVING POWER TO DISALLOW FURTHER DETECTOR MOVEMENT.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTJ OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTJ OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION..
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 63 LF-37-J349 CN 473 SP 7.2.2.2.1 REVISED FSAR TO DELETE REFERENCES TO THREE LOOP OPERATION CN 470 SP 7.2.2.2.1 REVISED THE FSAR TO DELETE REFERENCES TO THREE LOOP OPER-ATION, SINCE THE TECHNICAL SPECIFICATIONS DO NOT ALLOW THIS MODE OF OPERA-TION. PLANT SAFETY REMAINS UNALTERED BY THIS DOCUMENTATION REVISION.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE 00ES NOT INVOLVE AN INCREASE IN PROBAaILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTJ OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVEP PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTJ OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SA<ETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 69 Ni-d$-JC23 CMP 84-368d PROVIDED NEW DESIGN FOR ACCUMULATOR LEVEL TRENSMITTERS CMP 84-0638 PROVIDED A NEW DESIGN FOR ACCUMULATOR LEVEL TRANSMITTERS AND THE ASSOCIATED HYDRAULIC ISOLATION DEVICES. THE CHANGE FACILITATES CALISRATION OF LEVEL TRANSMITTERS. THE NEW TRANSMITTERS MEET ALL FUNCTIONAL REQUIREMENTS OF THE ORIGINAL TRANSMITTERS. (THIS CHANGE IS FULLY IMPLEMENTED.)
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTJ OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTJ OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY CUESTION DID NOT EXIST.
12CFRS3059 ANNUAL REPORT SUMMARIES s
OF UNION ELECTRIC APPROMED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 70 NE-So-0334 CMP 85-0297 REPLACED CHECK VALVES IN AIR SUPPLY LINES IN MSIV,MFIV A,CTUATORS CMP 85-0297 REPLACED CHECK VALVES IN AIR SUPPLY LINES WITHIN MAIN STEAM AND MAIN FEEDWATER ISCLATION VALVE ACTUATORS. THE REPLACEMENT INCREASES THE RELIA-BILITY OF THE VALVE 3 FOR NORMAL AND ASNORMAL CONDITIONS. THE NEW CHECK VALVES ARE FULLY QUALIFISD ENVIRONMENTALLY AND SEISMICALLY.
PURSUANT TO THE ADOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBA8ILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY JUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 71 NE-36-JJ43 CMP 84-3654 ADDED PERMANENT STORAGE FOR AIR COMPRESSORS IN CONTAIN1ENT
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CMP 84-0654 ADDED PERMANENT STORAGE FACILITIES FOR MAINTENANCE AIR COMPRESSORS IN THE CONTAINMENT SUILDING. THE CHANGE SAVED OUTAGE TIME IN MOVING COMPRESSORS IN AND OUT OF CONTAINMENT. RESTRAINTS PROVIDED WILL PREVENT COMPRESSORS FROM SECOMING MISSILES IN A SEISMIC EVENT. THE ADDITIONAL LOADING WAS ANALYZED NOT TO ADVERSELY AFFECT STRUCTURAL STEEL.
THE ATTACHMENTS OF MOTOR AND AIR COM-PRESSORS TO THE RECEIVER ARE DESIGNED FOR EXTENDED VIBRATORY SERVICE.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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10CFR50.59 ANNUAL REPORT SUMMARIES OF UNION ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 72 NE-66-J122 CMP 85-0296 ADDED AN ACCESS PLATFORM TO D/G SLDG FOR EASY ACCESS TO, FIRE DETECT CMP ES-0296 ADDED A PLATFORM TO ELEVATION 2332-3 0F THE DIESEL GENERATOR BLOG.
FOR EASY ACCES3 TO FIRE PROTECTION DETECTORS. THE DETECTORS ARE TESTED SEMI-ANNUALLY.
THE FSAR DRAWING WAS REVISED TO SHOW THE PLATFORM WHICH DOES NOT ALTER ANY ASPECT OF THE TECH. SPECS. OR THE HAIARDS ANALYSIS.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PR09A31LITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS LVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REJUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY 2UESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID T3 NE-87-JJ12 CMP $6-0105 CHANGED SETPOINTS FOR DIESEL GEN. ROOM VENT. FANS AND TEMP. CONTROL CMP 86-J105 CHANGED THE SETPOINTS FOR THE DIESEL GENERATOR ROOM VENTILATION F A;:S AND TEMPERATURE CONTROLLERS. CHANGE ALSO RAISED THE SETPOINTS FOR THE DIESEL GENERATOR LU3E OIL HEATERS AND JACKET WATER HEATERS. CHANGES REDUCE VENT FAN CONTINUOUS RUN TIME WITH THE DIESELS IN THE STANDBY MODEeWHILE RETAINING NORMAL SYSTEM OPERATION. RAISING HEATER SETPOINTS REDUCES THE OCCURENCE OF LOW TEMPERATURE ALARMS ON THE KEEPWARM SYSTEMS.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROSABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTI OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTI OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY OUESTION DID NOT EXIST.
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L 10CFR50.50 ANNUAL REPORT SUMMARIES l
OF UNION ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID i
74 NE-67-J242 OL 1957 SUsMITTED RELOAD LICENSE AMENDMENT FOR USE OF WESTINGHOUSE VANTAGE FUEL OL 1057 SUB91TTED THE RELOAD LICENSE AMENDMENT REVISIONS TO ALLOW THE USE OF VANTAGE 5 FUEL. SAFETYrENVIRONMENTAL,AND ACCIDENT EVALUATIONS JUSTIFY THE USE OF WESTINGHOUSE VANTAGE 5 FUEL THROUGH TRANSITION CORES OF MIXED FUEL FYPES TO A COMPLETE VANTAGE 5 CORE.
CHANGE WAS APPROVED BY THE NRC IN LICENSE AMEND-M Ert T-2 8.
PURSUANT TO THE A90VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE 3AFETY ANALYSIS RE-PORTJ OR CREATE POSSIBILITF FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-l GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY C'J E S T IO N DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 75 NE-87-dJ61 CMP 85-0452 MODIFIED RX TRIP SWITCHGEAR CA3. WIRING TO ALLOW FULL TESTING CMP 85-0452 MODIFIED THE REACTOR TRIP SWITCHGEAR CABINENT WIRING TO ALLOW FULt TESTING OF P-4 CONTACT MATRIX USING A PANEL MOUNTED SELECTOR SWITCH AND VOLT-METER. THE CHANGE SIMPLIFIES TESTING OF dREAKER SWITCH CONTACTS (P-4) USED IN SI BLOCK / RESET CIRCUITS IN THE SOLID STATE PROTECTION SYSTEM. THE MODIFIED CIR-CUIT USES EXISTING TEST SWITCH AND TERMINAL 80ARDSI AND THE TEST CIRCUIT DOES NOT AFFECT OPERATION OF THE 3REAKERS, NOR THE ABILITY OF THE RELAYS TO GENER-ATE A P-4 SIGNAL.
THE CHANGE DOESN'T ALTER EXISTING SAFETY ANALYSES OR MARGINS OF SAFETY.
PURSUANT TO THE A90VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTJ OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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10CFR50059 ANNUAL REPORT SUMMARIES OF UNION ELECTRIC APPROVE)
WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 76 NE-37-0252 ETP-EM-STJ4A,REV O PROCEDURE P40VIDED SYSTEM LINEUPS AND TECHNNICAL,FOR TEST ETP-EM-STJ4A,REV O PROCEDURE PROVIDED SYSTEM LINEllPS AND TECHNICAL DIRECTIUM FOR DIFFERENTIAL PRESSURE TESTING OF VARIOUS HIGH PRESSURE COOLANT INJECTION SYFTEM VALVES. THE TESTING OBTAINED VALVE STEM THRUST OPERATING REQUIREMENTS UNDER MAXIMUM DIFFERENTIAL PRES $URE GENERATED BY THE PUMPS IN THE SYSTEM. IN ALL CASES THE PRESSURES, TEMPERATURES,4ND FLOWS DIDNT EXCEED EQUIPMENT DESIGN LIMIT
S. PROCEDURE
INITIAL CONDITIONS ENSURE THAT PERFORMANCE DID NOT VIOLATE TECH SPECS.
PURSUANT TO THE ABOVE INFORMATION, THE' CHANGE DOES NOT INVOLVE AN INCREASE IN PRORAP.ILITY OF GCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFtTY OVER PREVIOd5 EVALUATIONS IN THE SAFEfY ANALY5IS NE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY GUESTION DID NOT EXIST.
REPORT S=FETY EVALUATION ITEM ID 77 NE-57-J253 RTO-ZZ-RLD55,REV 3 PROCEDURE PACKAGED OPENT FILTER WASTE IN RADLOC(-55 CONTAINE RTO-ZZ-RLD55,REV 0 PROCEDURE PACKAGED SPENT FILTER CARTRIDGES IN RADLOCK-55 ^
HIGH INTENSITY CONTAINERS. THE CONTAINERS PACKAGE UNSOLIDIFIED WASTES REQUIRING STABILITY FOR SHALLOW LAND DISPOSAL AT THE SARNWELL FACILITY. DURING TRANSFER OF THE SPENT CARTRIDGES TO THE CONTAINERS TWO PREVIOUSLY UNANALYZED ACCIDENTS COULD RESULT IN DROPPING A SPENT FILTER CARTRIDGE OR RUPTURING THE RADLOCK-55 CONTAINER. IN BOTH INSTANCES THE CONCERN WOULD BE FOR THE RELEASC 0F SOTH AIR-BORNE AND LIQUID CONTAMINATION TO THE PLANT ENVIRONMENT. ALL POSTULATED LEAKAGE OR SPILLS OF RADIOACTIVE MATERIALS WOULD BE CONTAINED WITHIN THE PLANT RADWASTE SYSTEM.
P182 5U ANT TO THE ASOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENC{ OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETT'0VER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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OF UNZON ELECTRIC QPPR00E0 WRITTEN SAFETY EVALUATIONS I
REPORT SAFETY EVALUATIJN ITEM ID 78 NE-97-J254 RFR NO.4442 DESIGNATED A STORAGE LOCATION FOR RX HEAD SHIELD LEAD BLANKETS, CONT RFR N0.4442 D2SIGNATED A STORAGE LUCATION FOR THE REACTOR HEAD SHIELDING LEAD BLANKETS AND CONTAINERS. THE FLOOR LOADING ABILITY WAS EVALUATED AS ACCEPTA8LE AT THE SPECIFIED LOCATION,AND THE LOCATION WILL INCLUDE STEEL COVERS TO ENCLOSE ANY COM9USTIBLE MATERIALS. THERE ARE NO SAFETY-RELATED COMPONENTS NEARBY.-
PUESUANT TO THE A90VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN y
- ROBA31LITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY A1ALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE l
OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-l GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
I THE EVALUATION DETERMIhED THAT AN UNREVIEWED SAFETY l'
CUESTION DID NOT EXIST.
I REPORT SAFETY EVALUATION I
ITEM ID l
79 NE-37-J255 ETP-BN-STJ31,REV 2 PROCEDURE ALLOWED DIFFEREN. PRESSURE MOVAT TEST ON VALVES 1
ETP-eN-ST301,REV 0 PROCEDURE PROVIDED THE VALVE AND SYSTEM LINEUPS TO PERFORM I
DIFFERENTIAL PRESSURE MOVAT TESTING ON VARIOUS 30 RATED REFUELING WATER STORAGE SYSTEM VALVES AND HIGH PRESSURE COOLANT INJECTION SYSTEM VALVES. THE TEST IS PERFORMED ONLY IN MODE SIX WITH THE CORE COMPLETELY OFFLOADED AND OPERABLE TRAINS OF ECCS OR RHR ARE NOT APPLICABLE. THE TEST LINE-UP DOESN'T OVERPRESSUR-IIE OR DAMAGE ANY COMPONENTS.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT.0R MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY GUESTION DID NOT EXIST.
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13CFR5JoS9 ANNUAL QEPORT SUMMARIES 3
OF UNION ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 80 NE-57-02od RFR N0.4261 REVISED FSAR 9.5.6 AND FIG 9.5.6-1 TO SHOW D/G SYSTEM VA,LVE LOCKED RFR NO.4261 REVISED FSAR 9.5.6.2.3 AND FIG.9.5.6-1 TO SHOW DIESEL GENERATORS AIR STAR 1 COMPRESSORS CROSS CONNECT ISOLATION VALVE LOCKED CPEN INSTEAD OF J'J S T NORMALLY OPEN. LOCKED OPEN JILL ENSURE THAT EITHER OF THE TWO STARTING AIR COMP-RESSORS CAN MAINTAIN AIR PRESSURE IN SOTH STARTING AIR TANKS. EMERGENCY SHUTDOWN IS NOT A SAFETY FUMCTION AND VALVE POSITION (OPEN OR CLOSE) DOES NOT AFFECT OPERABILITY.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROSA31LITY OF OCCURENCE ON CONSE3UENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 61 NE-87-J266 RFR NO.3954 EVALUATED TFE CLOSURE CAPABILITY OF FEEDWATER SYSTEM CHECK VALVES AFR NO.3954 EVALUATED THE CLOSURE CAPABILITY OF FEEDWATER SYSTEM CHECK VALVES AE-V-123,-121,-122,-123. THE EVALUATIOM VERIFIED THAT TOTAL CHECK VALVE BACK-LEAKAGE OF LESS THAN 250 GPM WOULD HAVE NEGLIG8LE' IMPACT ON CALLAWAY FSAR ArCI-DENT ANALYSES AND WOULD HAVE A VERY LOW POTENTIAL FOR WATER HAMMER IN THE F i-LINE.
PURSUANT s' O THE A90VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN IMCREA
'N PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF
.JUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE 6 ASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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1dCFR50.53 ANNUOL REPORT SUMMARIES OF UNION ELECTRIC APPROVED WRITTEN SAFETY EVALUATZONS REPORT SAFETf EVALUATION ITEM ID 82 NE-37-2283 CMP 67-1025 REPLACED THE CONTAINMENT COL __. VENT PLUGS WITH VENT VAL,VES AND CAP CMP 87-1325 REPLACED THE CONTAINMENT COOLER VENT PLUGS WITH VENT VALVES AND THREADED CAPS IN ACCORDANCE WITd VENDOR DESIGN STANDARDS. THE PIPIN3 ADDED WAS CALCULATED TO BE SEISMICALLY ACCEPTABLE AND IS ASME SECT IIIeCLASS 3 AS IS THE REST OF THE SYSTEM. THE CHANGE IMPROVED RELIABILITY WITHOUT IMPACTING CONTAIN MENT COOLER FUNCTION. THE CHANGE IS REFLECTED IN FSAR REVISION CN 469.
PURSUANT TO THE A30VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAL AN UNREVIEWED SAFETY GUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 83 NE-87-J237 CMP 87-1347 INSTALLED THE REACTOR VESSEL HEAD SHIELD CMP 67-1J47 INSTALLED THE REACTOR VESSEL HEAD SHIELD. THE SHIELD SYSTEM CON-SISTS OF A PEAMANENT SHIELD SUPPORT STRUCTURErREMOVAsLE LEAD WOOL SHIELD PANELS, AND THREE STORAGE CONTAINERS FOR THE SHIELD PANELS. THE WEIGHT OF THE HEAD SHIELD RESULTS IN HIGHER LOADS AND CORRESPONDING HIGHER STRESSES ON CERTAIN PLANT COMPONENTS. THE AFFECTED COMPONENTS INCLUDE THE HEAD LIFT RIG;THE POLAR CRANE ANS ITS SUPPORTS;THE REACTOR VESSEL N0ZZLES AND SUPPORTS;AND THE REQUIRE-MENT THAT THE PERMANENT SHIELD SUPPORT STRUCTURE NOT FAIL UN3ER SSE LOADS DURING PLANT OPERATION.
EVALUATIONS OF THESE COMPONENTS SUPPORT THE ADDITION OF THE SHIELD SYSTEM WEIGHT AS ACCEPTABLE. THE ADDITIONAL LOAD DOES NOT CAUSE ALLOWABLE STRESS LIMITS TO BE EXCEEDED. IN ADDITION THE PRIMER AND FINISH USED TO COAT THE PERMANENT STRUCTURE AND STORAGE 80XES IS ACCEPTA9LE FOR USE IN CONTAINMENT.
THIS CHANGE IS REFLECTED IN THE FSAR CN 474.
PURSUANT TO THE A30VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PR08 ABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF ECUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIE'JED SAFETY QUESTION DID NOT EXIST.
I
i 2BCFR5Jo99 ANNUAL REPORT SUMMARIES OF UNION ELECTRIC APPROVED W4ITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID d4 NE-37-J238 RMP 87-231$ INSTALLED SECOND AIR S OL E N'JI D VALVE JN MAIN TURBINE TURNING GEAR RMP 67-231d INSTALLED A SECOND AIR SOLENOID VALVE ON 3HE MAIN TUR8INE TURNING GEAR TO PROVIDE REDUNDANT VENTING OF THE TURNING G E 4i' PNEUMATIC CYLINDER. THE CHANGE PROVIDED REDUNDALT VENTING TO AVOID DAMAGE TO THE TURNING GEAR O' OULL GEAR. THE TURBINE AND TURBINE GEAR ARE NONSAFETY-RELATED SYSTEMS.
THIS CHANGE REVISED FSAR FIG 13.2-1.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-NENT IMPORTANT TO SAFETY OVE R PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A blFFERENT TYPE OVER PREVIOUS EV A',U ATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY GUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 85 NE-d?-2289 ETP-EM-ST0J3,REV 1 PROCEDURE CHANGE ADDED REFERENCE TO TS 3.1.2.5 ETP-EM-ST003,REV 1 PROCEDURE CHANGES INCLUDED ADDING A REFERENCE TO TECH. SPEC.
SECTION 3.1.2.5; TESTING VALVES BN-HV-8813 AND EM-HV-8835 WITH SAFETY INJECTION PUMP A IN-SERVICE RATHER THAN PUMP B; AND CHANGING PORTION OF TEST METHOD TO THROTTLE FLOW THROUGH VALVE EM-HV-8812A WHILE DIFFERENTIAL PRES $URE TESTING VALVE 5 BN-HV-8813 AND EM-HV-8835. TU AVOID A DECREASE OF FLOW BELOW THE MINIMUM FLOW REQUIREMENTS A CAUTION STATEMENT WAS ADDED. THE CHANGES DO NOT CONSTITUTE UNREVIEWED SAFETY QUESTIONS.
PUPSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OWER PREVIOUS EVALUATIONS IN THE 3AFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY,FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY GUESTION DID.10T EXIST.
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10CFR$30$9 ANNUAL REPORT SUMMARIES OF UNION ELECTOIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM IO 86 NE-6/-J367 CN 4ol SP 12.3,T12.3-2 REVISED FSAR HI ALARMS FOR RADIATION MONITORS, CN 481 SP 12.3,T12.3-2 REVISED FSAP FOR HI-ALARM AND HI-HI-ALARM FOR RADIATION MONITORS. THE REVISED ALARMS ALLOW ROUTINE STAGING OF DRUMS FOR RADVASTE SHIPMENTS WITHOUT ALARMING THE MONITORS. THE HI-ALARM OF A MONITOR USED DURING REFUELING ACTIVITIES WAS ALSO REVISED. IN EACH CASE THE REVISED ALARMS STILL SERVE THE FUNCTION OF ALERTING PERSONNEL TO ABNORMAL RADIATION LEVELS. THE AREA RADIATION MONITORING SYSTEM SERVES NO ACTIVE EMERGENCY JUNCTION AND IS NOT ESSENTIAL FOR SAFE SHUTDOJN.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PR09 ABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTI OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIchS IN THE SAFETY ANALYSIS REPORTI OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE dASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
- EPORT SAFETY EVALUATION ITEM ID 87 NF-87-JJdt OL 1863 TS 3/4.1.3.5 LICENSE AMENDMENT REDEFINED RODS FULLY WITHDRAWN OL 1963 TS 3/4.1.3.5 LICENSE AMENDMENT REDEFINED RODS FULLY WITHDRAWN AND ALSO REVISED FIG 3.1-1 FOR S AME DEFINITION. SECAUSE OF RODLET WEAR ON RCCA CONTROL RODS, WESTINGHOUSE RECOMMENDS REPOSITIONING RCCAS TO AVOID WEAR IN ONE LOCATION.
THIS TECH SPEC CHANGE DEFINES FULLY WITHDRAWN AT 225 STEPS OR HIGHER,INSTEAD OF AT 228 STEPS. THIS WOULD ALLOW RODS FULLY WITHDRAWN AT 225 STEPS WHICH IS LESS THAN J.3 INCHES INTO THE ACTIVE CORE. CALCULATICCS VERIFY THAT THIS INSERTION INTO ACTIVE CORE HAS MINIMAL IMPACT ON POWER DISTRIBUTIONS,0N PEAKING FACTORS, OR ON SHUTDOWN MARGIN.
THIS CHANGE WAS SUB9ITTED AND APPROVED $Y THE NRC AS LICENSE AMENDMENT-29.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTI OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTI OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE dASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINE 4 THAT AN UNREVIEWED SAFETY QGESTION DID NOT EXIST.
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10CFR5J.59 ANNUAL REP 3RT SUCMARIES OF UN20N ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SA!'TY EVALUATION ITEM ID 88 OC E4-JJ27 CMP $4-01$4 REPLACED STEM AND PACCING ON MSIV ACCUMULATOR SHUTOFF VALVES CMP d4-3164 REPLACED STEM, PACKING ON MSIV ACCUMULATOR SHUT 0FF VALVES. IT REPLACED SOFT-SEATED STEM AN3 TEFLON PACKINS ON MSIV ACCUMUL. SHUTOFF VALVES WITH HARDSEATED STEMS AND VITON PACKING TO ENSURE DESIGN LIFE OPERASILITY AND TO UPGRADE FOR ACCIDENT CONDITIONS. (THIS CHANGE IS FULLY IMPLEMENTED.)
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DE' ERMINED THAT AN UNREVIEVED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 89 OA-a?-0029 CMP S4-3137 REPLACED THE GOULD RUNDELL FOUR POSITION HAND $ WITCHES CMP 84-0137 REPLACED THE FOUR P3SITION HANDSWITCHES FOUND IN MOTOR CONTROL CEN-TER CUSICLES WITH WESTINGHOUSE FOUR POSITION SWITCHES. THE NEW SWITCHES PERFORM THE SAME FUNCTION AS THE REPLACED SWITCHES,.SUT REPRESENT A MATERIAL CHANGE AND DESIGN UPGRADE.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOE 5 NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSECUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPCRT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED Th.f AN UNREVIEWE0 SAFETY QUESTION DID NOT EXIST.
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13CFR50059 ANNUAL REPORT SUMMARIES OF UNION ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 9d NE-35-JJ58 CMP e4-0018 INSTALLED A CORROSION MONITORING SYSTEM FOR COMPONENT C0;0 LING SYSTE CMP 84-2218 INSTALLED A CORROSION MONITORING SYSTEM FOR THE COMPONENT COOLING WATER SYSTEA. THE CORROSICN MONITOR $NG EQUIPMENT DOESN'T PERFORM A SAFETY RELA-TED FUNCTION OTHER THAN TO MAINTAIN THE PRESSURE BOUNDARY INTEGRITY. CORROSION METER PROSES ARE INSERTED IN THE FLUID STREAM. THE MONITORING SYSTEM PROSES ARE METALLIC AND SEISMICALLY ANALYZED TO MAINTAIN PRESSURE BOUNDARY INTEGRITY DUR-ING AND FOLLOWING AN SSE. THE SYSTEM INCLUDED INSTALLATION OF A CORROSION TEST COUPCN RACK AND METER. THE MONITORING SYSTEM CIRCU1FERENTIAL PRESSURE BOUNDARY AREA IS SOUNDED BY FSAR ANALYSIS OF COMPONENT COOLING WATER SYSTEM POSTULATED MODERATE ENERGY CRACK CONFIGURATION. INST ALL AT ION AND PHYSICAL LAYOUT MAKE RE-MOTE THE PR09 ABILITY OF A COMPONENT BREAK AJAY AND TRAVEL BACK TO PUMP SUCTION.
FURTHERrINSTALLATION AT LOW POINTS AND IN SELECT AUX BUILDING LOCATIONS PREVENT SPRAY FROM A POSTULATED BREAK IN PRESSURE SOUNDARY FROM AFFECTING SAFETY RELATED EQUIPMENT OR THE TWO COMPONENT COOLING WATER TRAINS. INSTALLATION OF THIS SYSTEM ALLOWS CONTIhu005 CORROSION MONITORING CAPA3ILITY AND A CORROSION HISTORY IN EACH TRAIN OF CCWS.
PURSUANT TO THE ABOVE INF OR.t A TION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MEMT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTI OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN T H E. SAFETY ANALYSIS REPORTI OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECAFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 91 NE-36-JJ79 CMP 85-0116 MODIFIED STARTUP LOGIC ON ESS. SERV. WATER PUMPS FOR LOSS OF POWER CMP 85-0116 MODIFIED THE STARTUP LOGIC $0 THAT SOTH ESSENTIAL SERVICE WATER (ESW)
PUMPS ARE STARTED ON A LOSS OF POWER TO EITHER SAFETY BUS NB01 OR N322. THIS CHANGE ELIMINATED A NEED FOR THE OPERATORS TO MANUALLY START AN ESW PUMP. THE CIRCUITRY IS CLASS IE AND HAS REDUNDANT ISOLATION FROM CLASS IE 4163V dUSSESI PRES $URE SWITCH INSTALLATIONS ARE SEISMICALLY SUPPORTEDIAND THE INCREASE IN FIRE LOADIN3 IS NEGLIGIBLE. CONSEQUENCES OF PREVIOUSLY ANALYZED OR NEW TYPES OF MALFUNCTIONS OR ACCIDENTS ARE NOT INCREASED OR CREATED.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY ^VER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTI OR CREATE POSSIBILI.I FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTJ OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY
.00ESTION DID NOT EXIST.
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1JCFR50059 ANNUAL REPORT SUMMARIES 0F UNION ELECTRIC 4PPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 92 NE-SS-0198 CMP 85-2147 REPLACED EXISTING INSTRUMENTATION IN THE PROCESS SAMPLIN,G SYSTEM CMP 85-0147 REPLACED EXISTING CALGON SODIUM ANALYZERS IN THE PROCESS SAMPLING SYSTEM WITH ORION MODEL SODIUM ANALYIERS. THE CHANGE SHOULD INCREASE SYSTEM RE-LIA3ILITY AND REDUCE MAINTENANCE AND OPERATION 4L PROBLEMS. THE CHANGE REQUIRED A REVISION TO FSAR FIG. 10.4-7. THE CHANGE DOES NOT ADVERSELY IMPACT PLANT SAFETY.(THIS MODIFICATION HAS BEEN FULLY IMPLEMENTED.)
PURSUANT TO THE Ah0VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PRoeABILITY OF OCCURENCE 09 CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALU4TIONS IN THE SAFETY ANALYSIS RE-PORT; OR CaEATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALU4TIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR 4NY TECHNICAL SPECIFICATION.
THE EVALU4 TION DETERMINED TH4T AN UNREVIEWED SAFETY QUESTION DID NOT EXI$l.
REPORT SAFETY EVALUATION ITEM ID 93 NE-87-011C RMP 87-2335 REPLACED NONSAFETY-RELATED PIPING (MSR SHELL DRAIN LINES)WITH SS RMP 87-2035 REPLACED MONSAFETY-RELATED PIPING (MSR SHELL DRAIN LINES)WITH STAIN-LESS STEEL. THE MATERIAL CHANGE WILL RESIST PIPE THINNING AND FAILURE DUE TO EROSION / CORROSION. THE CHANGE INVOLVES NONSAFETY-RELATED COMPONENTS INSIDE THE TUR8INE 3LDG. FSAR FIGURE 13.2-1 WAS MODIFIED.
PURSUANT TO THE A30VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IM*0RTANT TO S4FETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTJ OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALU4 TION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 74 NE-37-2253 RFR NO.455J REVISED FSAR FIG 5.4-7 TO SHOW VALVE EJ-V154 AS LOCKED CLOSED
.CFR NO.4553 REVISED FSAR FIG 5.4-7 TO SHOW THE VALVE EJ-V154 AS LOCKED CLOSED.
THE USE OF THE LOCK PLACED MORE STRINGENT CONTROLS ON THE OPERATION OF THIS VALVE WHICH IS CLOSED IN BOTH ITS NORMAL AND ACCILENT POSITION.
PURSUANT TO THE A90VE INFORMATTON, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN,0F SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
.THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION PiD NOT EXIST.
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L 10CFR50.59 AhNUAL EEPORT SUMMARIES OF UNION ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS I
l OEP0kT SAFETY EVALUATION ITiM ID l
95 NE-87-J234 RFM No.4511 REVISED FSAR TABLE 3.11(B)-3 F3R TYPO ERROR ON COMPONENT, DESIGNATI0 l
l RFR ho.4511 REVISED FSAR TABLE 3.11(83-3 FOR A TYPING ERROR CORRECTION IN DESIG NATION FROM GNHI517A TO GNH517A. GNH517A AND GNHI517A PROVIDE LOCAL CONTROL FOR CONTAINMENT COOLER FAN SGN010. THE CORRECTION OF THE TYPO DOES NOT IMPACT THE FUNCTION OF THESE SWITCHES. THE CHANGE Is REFLECTED IN FSAR CN 493.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN i
PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-l MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
I REPORT SAFETY EVALUATION ITEM ID 76 NE-87-J311 ETP-KB-ST034, KEV O PROCEb*tE TcSTED ALL BREATHING AIR HOSE STATIONS FOR AIR QUA ETP-KB-STSJ4,REV O PROCEDURE WAS DEVELOPED TO TEST ALL BREATHING AIR H0SE STATIONS FOR GRADE D QUALITY AIR AND PARTICULATES. THE PROCEDURE VERIFIED AIR QUALITY AT EACH INDIVIDUAL HOSE STATION THROUGHOUT THE SREATHING AIR SYSTEM.
THIS PROCEDURE PROVIDED A TEST THAT IS CURRENTLY NOT IN THE FSAR.
P' RSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE JN J
PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-I MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT;-OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE dASIS FOR ANY TECHNICAL SPECIFICATION.
1 THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY uuESTIUN DID.NOT EXIST.
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13CFR$2.59 ANNUAL REP 00T SUMHARKES OF UNION ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALdATION ITcM ID 97 NE-b7-J235 CMP 87-104J DOCU9ENTED VANTAGE-5 FUEL LOAD, RECONSTITUTION OF OFA/ LOP,AR FUEL ASS CMP 87-1243 DOCUMENTED THE LOADING OF WESTINGHOUSE VANTAGE-5 FUEL IN THE CYCLE THREE CORE, AND RECONSTITUTION OF OFA AND LOPAR FUEL ASSEMBLIES. WESTINGHOUSE EVALUATIONS DETERMINED THAT THESE ACTIVITIES DO NOT RESULT IN ANY VIOLATIONS OF SAFETY OR ACCIDENT LIMITS. THIS CHANGE IS ASSOCIATED WITH TECH $PEC CHANGES OL-1057 AND OL-1059.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A O!FFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY As DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY LVALUATION ITEM ID 95 NE-37-J340 CMP 67-111J ADDED SAMPLE VALVE HF-V-973 TO SEC. WASTE SYS. GAS COOLER CONDENSATE CMP 87-1113 ADDED A SAMPLE VALVE HF-V-973 TO ALLOW SAMPLING THE CONDENSATE THAT DRAINS FROM THE HEATER VENT GAS COCLER.
THE SAMPLI POINT ALLOWS CHEMISTRY PERSONNEL AN ADDITIONAL SAMPLE POINT FOR CONTAMINATION. DESIGN PRESSURE AND TEMPERATURE REQUIREMENTS ARE MAINTAINED. THE SECONDARY LIQUID WASTE SYSTEM IS NOT SAFETY-RELATED AND ADDING THE SAMPLE POINT DOES NOT ADVERSELY IMPACT PLANT SAFETY.
PURSUANT TO THE A30VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBAdILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OWER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTI 04 CREATE POSSIeILITY FOR ACCIDENT OR' MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTI OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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I 12CFR50.59 ANNUAL REPORT SUnMwRIES OF UNION ELECTRIC APPROVED l
WRITTEN SAFETY EVALUATIONS l
I l
REPORT SAFETY WVALUATION ITEM ID 99 NE-$7-a341 RFR No.4759 CORRECTED ROOM NUM3ER AND LOCA CLASS.FOR DAMPER GKD3J25(FSAR TABLE)
RFR NO.475? CORRECTED THE ROOM NUMBER AND THE LOCA CLASSIFICATION F3R THE ACCESS CONTROL EXHAUST ISOLATION DAMPER GKDeJ25. THE REVISIONS WERE REQUIRED TO FSAR TABLE 3.11 ( J). 3.
THE CORRECTIONS TO THE DOCUMENT IN NO WAY IMPACTS PLANT SAFETY.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PR39 ABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPDATAh! TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORf; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY OUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 133 NE-67-J342 RMP 87-2034 DELETED FLOW RESTRICTING ORIFICES IN MAIN FEEDWATER PUMP SEAL RETUR RMP 87-2034 DELETED FLOW RESTRICTING ORIFICES IN THE MAIN FEEDWATER PUMPS (PAE21A
,9) SEAL WATER RETURN LINES. "HE ONLY IMPACT FROM REMOVING THE ORIFICES IS THE POTENTIAL EROSION OF PkES$URL CONTROL VALVE INTERNALS AND ADJACENT DOWNSTREAM PIPING. THESE LINES WERE ADDED TO THE EROSION-CORROSION PRCGRAM FOR PERIODIC MONITORING OF PIPE WALL THICKNESS. THIS EQUIPMENT PERFORMS NO SAFETY-RELATED OR TECH SPEC FUNCTIONS OR REGUIREMENTS.
PUR$UANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY CVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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10CFR53059 ANNUQL DEP3QT SUMMARIES s
OF UN80N ELECTRIC APPQ0VED WRITTEN SAFETY EVALUATION 3 REPORT SAFETY EVALUATION ITEM ID 141 LF s7-J344 OL 1071 TS FIG 6.2-2,1 REVISED TECH SPEC ORGANIZATION CHARTS OL 1071 TS FIG 6.2-2,1 HEVISED TECH SPEC ORG4NIZATION CNARTS TO REFLECT ORGANIZATIONAL CHANGES. CHANGES INCLUDE THE LICENSING AND FUELS DEPT, ENGINEERING DEPT,20ALITY CONTROL,AND ADMINISTRATION SERVICES. CHANGES DIDN'T REDUCE THE OVERALL EXPERIENCE BASE NOR MINIMUM CUALIFICATIONS, AND WERE, APPROVED BY THE NRC IN LICENSE AMENDMENT-32.
PJkSUANT TO THE ASOVE INFORMATION, THE CHANGE DCf5 NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVEA PREVIGUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTJ OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANT TECHNICAL' SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
RZPORT SAFETY EVALUATION ITEM ID 102 NE-37-0241 OL 1054 REVISED TS SECTION 6.0,3/4.3.3.7,3/4.7.10,4ND LICENSE ON FIRE PROCTECTI OL 1054 REVISED TS SECTIONS 3/4.3.3.7,3/4.7.13,3/4.7.11 AND BASES,6.9,AND LICENSE CONDITIONS 2.C.(5) CONCERNING FIRE PROTECTION. CHANGE INVOLVED REMOVAL OF REQUIREMENTS RELATED TO FIRE PROTECTION FROM THE TECHNICAL SPECIFIC ATIONS AND PLACING THEM IN THE FSAR AND PLANT PROCEDURES. NO DESIGN CHANGE OR TESTING WAS INVOLVED. CHANGES WERE CONSISTENT WITH GENERIC LETTER 86-13, AND WERE AP-PROVED BY THE NRC IN LICENSE AMENDMENT-30.
PURSUANT TO THE A50VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PR39 ABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTJ OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEVED SAFETY QUESTION DID NOT EXIST.
13CFR50.59 ANNUAL REPORT SUMMARIES OF UN20N ELECVRIC APPQ0VED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID IJ3 hE-dT-J232 CMP $6-1925 REPLACED S/G BLOWDN HEAT EX.TUSE BUNDLES AND CHANGED GASfET CMP 66-1025 REPLACED STEAM GENERATOR BLOWDOJN HEAT EXCHANGER TUBE BUNDLES WITH BUNDLES THAT ALLOW GREATER FLOW AND ALSO CHANGED GASKET TO IMPROVE SEALING.
ORIGINAL TudE BUNDLES WERE DAMAGED BY EXCESSIVE CONDENSATE FLOW THROUGH THE SHELL SIDE OF THE HEAT EXCHANGER. THE REPLACEMENT BUNDLES ARE CONSTRUCTED OF THE SAME QUANTITY,$IIE,AND MATERIAL AS THE ORIGINAL. THE HEAT EXCHANGER PERFORMS NO SAFETY-RELATED FUNCTION.
THIS CHANGE IS REFLECTED IN THE FSAR CHANGE CN 478 PURSUANT TO THE A90VE INf 3RM ATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT 01 MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY GUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 1J4 NE-ST-4331 OL 1065 TS 4.11.2.5 AND TA3LE 4.3-3 REVISED TO CORRECT ERROR AND WRONG REFERENC OL 1065 TS 4.11.2.5 AND TABLE 4.3-3 WFRE REVISfD TO CORRECT AN ERROR IN REFERENCE AND TO DELETE AN ITEM THAT DID NOT BELONG IN THE TABLE. THE CHANGES WERE PURELY ADMINISTRATIVE IN NATURE. THE CHANGES WERE SU9MITTED AND APPROVED BY THE NRC AS LICENSE AMEND 9ENT-31.
PUPSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OWER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION C F A DIFFERENT TYPE OVER PREVIOUS EVALUATIch$ IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE HAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWCD SAFETY GUESTION DID NOT EXIST.
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10CFR53.59 ANNUAL QEPORT SUMMARIES f
0F UNICN ELECTRIC APPROVED I
WRITTEN SAFETY EVALUATIONS I
l REPORT SAFETY EVALUATION i
ITEM 13 1J5 NE-63-JJJ7 CDP-ZZ-22440,REV 5 PROCEDU4E ADDED NITROGEN SPARGE OF TME CONDENSER,HOTWELL l
CDP-ZZ-00463,REV 5 PROCEDURE ADDED A SECTION TO ALLOW NITROGEN SPARSE OF THE NOTWELL. THIS ALLOWED AIR INLEAKAGE TESTING. NITROGEN WAS ADMITTED THROUGH EXISTINS ROOT VALVES INSTALLED SELOW THE WATER LINE. THE FLOW WAS ADMINISTRA-TIVELY LIMITED TO 24 CFM TO ALLOW THE VACUUM PUMPS TO MAINTAIN VACUUM.
THE MAIN CONDENSER AND THE CONDENSER AIR HEMOVAL SYSTEM ARE NOT SAFETY-RELATED.
PURSUANT TO THE A80VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITT OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 126 NE-36-J339 RTN-BM-3BJJ1,REV 6 PROCEDURE PROVIDED SINGLE BED SERIES FOR S/G BL3WDN DEMIN.8E RTN-SM-000' 1,R EV 6 PROCEDURE PROVIDED A SINGLE BED S!sIES ALIGNMENT FOR THE J
STEAM GENERATOR BLOWD06N MIXED SED DEMINERALIZERS. SINSLE BED SERIES PROCESSING, WITH ACTUAL FLOW THROUGH THE DEMIN. LESS THAN DESIGN FLOW, PREVENT $ UNNECESSARY RESIN EXHAUSTION AND ALLOWS aETTER RESIN PERFGh(ANCE. TO MINIMIZE A POSSIBILITY OF A RETENTIGN ELEMENT FAILURE, THE BED IS REPLACED AT AN ADMINISTRATIVE LIMIT BELOW DESIGN FOR DIFFERENTIAL PAESSURE. IN ADDITION FLOWRATES IN THE SINGLE dED SERIES ARE BELOW DESIGN FLOW.
PURSUANT TO THE A30VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IFPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY A4ALYSIS RE-PORT; OR CREATE POSSI61LITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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10CFR52.59 ANNUAL REPORT SUMMARIES Of UNION ELECTRIC APPROVED WRITTEN S a r t T C'.* *
- 834 TI O NS REPORT SAFETY EVALUATION ITEM ID 1J7 NE-ds-4J23 RFR NO.4779 DELETED THE REFERENCE TO SPECIFIC CORROSION MONITOR /FS AR, FIG 1f.4-1 RFR NO.4779 DELETED THE REFERENCE TO A SPECIFIC CORROSION MONITOR (MCM-DA-5301)
FROM FSAR FIG 10.4-1. THE LOCATION OF THE CON 3ENSER TUSE CORROSION MONITORIMG EQUIPMENT WILL SE LISTED AS A CORROSION MONITORING SAMPLE POINT WITHOUT IDENT-IFYING A SPECIFIC INSTRUMENT. THIS CHANGE ACCOMODATES ANY CHANGES IN VENDORS OR EQUIPMENT. THE DOCUMENTATION CHANGE DOES NOT IMPACT THE DESIGN OR FUttCTION OF THIS NONSAFETY-RELATED EQUIPMENT.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT I"*0RTANT TO SAFETY OVER PREVIOUS EVALUr410NS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT Aa MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE 9 ASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEVED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITSM ID 1J8 NE-88-J026 RMP 85-22d3 E%CAPSULATES PIPING IN THE CONDENSATE SYSTEM AND REVISES FSAR FIG RMP 88-20d3 ENCAPSULATES PIPING IN THE CONDENSATE SYSTEM AND REVISES FSAR FIG 4
10.4-7 ENCAPSULATION OF HEATER VENT LINES (AD-114-HSD-2.5,AD-115-H9D-2.5)WAS REQUIRED DUE TO SERIOUS EROSION IN THE PIPING. THE REPAIR INCLUDES ENCAPSULATION WITH STAINLcSS STEEL PIPE AND EL60US. THE REPAIR ALLOWS THE LINES T3 FUNCTION 6
AS DESIGNED,TO MAINTAIN THE PRESSURE dASED ON SERVICE CONDITIONS,AND TO PREVENT PIPE WHIP IF THE EROSION WAS NOT CONTAINED. THE ADDITIONAL WEIGHT OF THE ENCAPSULATION IS SUPPORTED ADEQUATELY BY EXISTING SUPPORTS.
PURSUANT TO Tdt AdOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBA91LITY OF OCCURF"Ce os CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT 10 SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF.A DIFFERENT TYPE CVER *REVIOUS EVALUATIONS IN THZ SAFETY ANALYSTS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY CUESTION DID NOT EXIST.
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m 12CFR59.59 ONNUAL QEPORT SUMMARIES 0F UNION ELECTRIC APPROVED WRITTEN SAFETY EbALUATIONS REPORT SAFETY EVALUATION ITEM 10 199 NE-3d-JC2d CN 436 SP 12.2.3.4.2.2 REVISED FSAR REQUIREMENT FO' LA8. ISOTOPIC ANgt OF RAD.M0 CN 48o SP 12.2.3.4.2.2 REVISED THE FSAR FOR THE REQUIREMENT OF PERIODIC CART-RIDGE FILTER REMOVAL FOR LA30RATORY ISOTOPIC ANALYSIS FOR AUXILIARY BLDG VENTILATION RADIDACTIVITY MONITOR GL-RE-62. THESE AIR SAMPLES PROVIDE INFORMA-TION FOR TRENDING ONLY AND MUST BE ANALYZED FOLLOWING HIGH ACTIVITY ALARMS.
THE TRENDING INFORMATION FROM THIS MONITOR IS ALSO AVAILABLE FROM A PANEL IN THE CONTROL ROOM. IN ADDITION THE MONITOR SUPPLEMEN15 THE ROUTINE AUX.8LDG AIR SAMPLING PROGRAM GIVEN IN PROCEDURE HOP-ZZ-03003rRA010 LOGICAL SURVEY PROGRAM.
PURSUANT TO THE A30VE INFORMATIONs THE CHANGE DOES NOT INWOLVE AN INCREASE IN i
PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT 19PORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN TK2 SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-
'i GIN OF SAFETY AS DEFINED IN THE dASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 11J NE-d7-J249 RMP $7-2021 PROVIDED RELIEF VALVE ON RETURN PIPING FROM CONDENSATE DEMIN. COOLER RMP $7-2021 PROVIDED A RELIEF VALVE ON THE RETURN PIPING FROM THE SAMPLE COOLERS SERVING THE CONDENSATE DEMINERALIZERS. A CHILLEM UNIT COOLS SAMPLES USED TO MONITOR THE PERFORMANCE OF THE CONDENSATE DEMINERALIZER SYSTEM. THIS SYSTEM SERVES NO SAFETY FUNCTION AND THE MODIFICATION INCREASES THE RELIABILITY OF THE CHILLER UNIT. IN THE EVENT OF A PRIMARY TO SECONDARY LEAK, ACTUATION OF THE RE-
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LIEF VALVE HAS NO ADVERSE IMPACT SINCE ANY DISCHARGE IS ROUTED TO THE CONDENSER PIT LIQUID RADWASTE SUMP.
PdRSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBAdILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR M4LFUNCTION OF A DIFFERENT TYPE I
OVER PREVIUUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-
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GIN OF SAFETY AS DEFINED IN THE SASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETEaMINED THAT AN UNREVIEWED SAFETY j
QUESTION DID NOT EXIST.
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13CFR53.59 ANNUAL REPORT SUMMARZES OF UNION ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 111 NE-$7-J258 CMP 87-1297 EVALUATED PLANT OPERATION WITH 55 TENSIONED STUDS IN RX, VESSEL CMP 37-1397 EVALUATED PLANT OPERATION WITH 53 TENSIONED STUDS IN THE REACTOR VESSEL INSTEAD OF 54 STUDS TENSIONED. WESTINGHOUSE PERFORMED CALCULATIONS THAT CONFIRM THAT CONTINUED PLANT OPERATION IS ACCEPTABLE WITH ONE STUD LEFT UN-TENSIONED AND THAT THE ASME S$PV CODE STRESS INTENSITY LIMITS ARE MET AND THE REACTOR VESSEL 0-RINS WOULD REMAIN SEALED.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROSABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY CWER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTI OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEN ID 112 NE-67-J299 CL 1234 TS T3.6-1 INCHEASED MAX. ISOLATION TIME FOR MINI-PURGE ISO. VALVES OL 1034 TS T3.6-1 INCREASED FROM THREE TO FIVE SECONDS THE MAXIMUM ISOLATION TIME FOR MINI-PURGE ISOLATION VALVES GT-HZ-24,05,11,12. THE THREE SECOND STROKE TIME IS OVERLY CONSERVATIVE SINCE THE VALVES MEET ALL LICENSING CRITERIA GIVEN A.FIVE SECOND STROKE TIME. INIS CHANGE HAS 3EEN SO9MITTED AND APPROVED BY NRC AS LICENSE AMENDMENT-33.
PURSUANT TO THE ABOVE INFORMATION, THE CHANSE DOES NOT INVOLVE AN INCREASE IN PR3BABILITY OF OCCURENC[ OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQdIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTI 04 CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL $PECIFICATION.
4 THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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12CFR53.59 ANNUDL QEPO4T SUMMORIES y
OF UNION ELECTeIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION I_
ITEM IO 113 NE-37-4303 OL 1267 TAdLE 4.3-1 REVISED TO COMPLY WITH GENERIC LETTER 85-09 CL 1067 TABLE 4.3-1 WAS REVISED TO COMPLY WITH NRC GENERIC LETTER 85-09 AND STAFF GUIDANCE TO INCLUDE FUNCTIONAL TESTING REQUIREMENTS FOR REACTOR TRIF BYPASS BREAKERS PRIOR TO PLACING THEM IN SERVICE DURING MONTHLY TESTING AND DURING REFUELING CUTAGES. THIS CHANGE WAS SU9MITTED AND APPROVED BY THE NRC AS LICENSE AMENDMENT-34.
PURSUANT TO THE A30VE INF ORM ATION, THE CHANGE DOES NOT INVOLVE AN INCAEASE IN PRoeABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTIOK OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-l PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE
- OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
I THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY OUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 114 NE-S$-JJJ6 OTS-EP-203J1,REV 3 PROCEDURE TO VERIFY ACCUMULATOR DISCHARGE CHECK VALVE FLOW OTS-EP-DJJJ1,REV 0 PROCEDURE VERIFIED THE ACCUMULATOR DISCHARGE CHECK VALVE FLOW. THE METHOD INCLUDED DISCHARGING A SMALL AMOUNT OF BORIC ACIS WITH GREATER THAN 203BPPM BORIC ACID INTO THE RCS VIA NORMAL ACCUMULATOR INJECTION ECCS FLOW-PATH. THE PLANT WAS IN MODE 4 WITH A STEAM 3UBBLE IN PRESSURIZER AND RCS PRESS-URE EELOW 4ACPSIG BUT ABOVE 325PSIG. ACCUMULATOR PRESSURE AND LEVEL AND RCS PRESSURE WEAE RECORDED DATA TO DOCUMENT SATISFACTORY FLOW FROM THE ACCUMULATOR THROUGH LISTED CHECK VALVES. THE TEST INVOLVED A CONTROLLA8LE PROCESS SY MAIM-TAINING LOW PRESSURES, LOW DISCHARGE RATES,MONITORINS,AND ONLY THE MANIPULATION OF ACCUMULATOR SYSTEM VALVES WHICH NAVE NO AUTOMATIC SAFETY ACTUATION FUNCTIONS.
PURSUANT TO THE A90VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBA8ILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTI OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY CUESTION DID NOT EXIST.
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12CFR52039 ONNUAL REPORT SUMMARIES OF UNION ELECTOIC APPOOVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID OTN-EP-3J2J1,REV 3 PROCE9URE M3DIFICATION TO RECIRCULATE SI ACCUMULATORS 115 NE-66-@JJS OTN-EP-32231,REV 3 PROCEDURE ADDED A SECTIO 1 TO ALLOW RAISING THE 80RON CON-CENTRATION OF AN ACCUMULAT0A BY RECIRCULATING WATER IN THE REFUELINE WATER STORAGE TAN < THROUGH THE AFFECTED ACCUMULATOR. THE METHOD PROVIDES CONTINUAL DRAIA AND PERIODIC REFILL TO MAINTAIN THE BORON CONCENTRATION WITHIN TECH SPEC LIMITS. FSAR ANALYSES ALLOJ PUMPING BORATED WATER FROM THE RWST TO THE ACCUMU-LATOR. ADDITION OF WAT(R FROM THE ACCUMULATOR IS ADMINISTRATIVELY CONTROL 50 THAT RWST B3RON CONCERTRATION REMAINS WITHIN LIMITS.
PURSUANT TO THE AaQVi INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCU%2hCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNffl0N OF EQUIP-MENT IMPO4 TANT TO S.AFITY OWER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTI OR CREATE PO'SSCSILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVAldA.TIONS IN THE SAFETY ANALYSIS REPORTI OR AEDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE MASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATIOW DETERMINED THAT AN UNREVICWED SAFETY QUESTION DID AST EXIST.
REPGRT SAFETY EVALUATION ITEM ID 116 NE-33-JJ13 RFR NO.4S T9 AEVISED FSAR TABLES 6.2.4-1,3.9(N)-12 FOR EM SYSTEM VALVES RFR NO.4979 REVISED FSAR TABLES 6.2.4-1,3.9(N)-10 FOR HIGH PRESSURE COOLANT INJECTION VALVES EM-HV-3871,EM-HV-8964.
THIS REVISICN ALLOWS THE VALVES TO BE LEFT OPE 4, THE VALVES ARE CONTAINMENT ISCLATION VALVES FOR THE SAFETY INJECTION TESr lid?.
THESE ARE ACTIVE VALVES AND ARE CAPABLE OF CHANGING STATE TO MEET TNE!A SAIETY FUNCTION. THE VALVES CLOSE DURING AN ACCIDENT. THE VALVES ARE LEFi CPUN ONLY AS REQUIRED TO VENT SAFETY INJECTION TEST LINE PRESSURE. THE TWO VALVES ARE REDUNDANT AND A SINGLE ACTIVE FAILURE WOULD ONLY PREVENT ONE OF THE VALVty FROM CLOSING. THE TEST PROGRAM ENSURES THAT THE VALWES CLOSE AS REQUIR-ED AFs PEET LEACAGE # ATE LIMITS ON A CISA SIGNAL.
PUkSUANT TO THE A80VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTAhT TO SAFETY OWER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTI OR CREATE POSSISILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTI OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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I REPORT SAFETY EVALUATION
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ITEM ID 117 NE-b3-2319 RFA NO.4917 REVISED FSAR FIG v.2-2 TO SHOW V ALVE EF-V222 LOCKED CLO S,E D RFR NO.4917 REVISED FSAR FIG 9.2-2 TO SHOW THE ESSENTIAL SERVICE WATER VALVE EF-W222 LOCKED CLOIED. THE USE OF THE LOCK PUTS MORE STRINGENT CONTROLS ON OPERATION OF THE VALVE. THE VALVE 15 h0RMALLY CLOSED AND ITS ACCIDENT POSITION l
IS CLOSED.
PURSUANT TO THE A30VE INFORMATION, THE CHANGE CDES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSISILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTI OR REDUCE THE MAR-GIN OF 3AFCTY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETf GUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 118 NE-83-JJ24 RFR NO.4562 REVISED FSAR FIG.9.4-6 TO REFLECT AS-9UILT CONDITIONS FOR GR SYSTEM RFA NO.4562 REVISED FSAR FIG 9.4-6 TO REFLECT AS-8UILT CONDITIONS. THE CHANGE ADDED TEN VALVES AND TWO PRESSURE DIFFERENTIAL SWITCHES AND DELETED FOUR VALVES.
ALL REVISIONS WERE MADE TO DOCU1ENTATION OF THE CONTAINMENT ATMOSPHERE CONTROL SYSTEM. THIS IS A NONSAFETY-RELATED SYSTEM.
PURSUAhT TO THE A30VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROEABILITY OF OCCURENCE OP CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IPPORTANT TO SAFETY OVER PPEVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POS$IBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINE 3 THAT AN UNREVIEWED SAFETY QUESTION DID NOT EMIST.
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12CF450.59 ANNUAL REPORT SUMMARIES CF UNION ELECTRIC APPROVED WRITTEN SAFETY E V ALU A TI ON S L
REPORT SAFETY EVALUATION ITEM ID 119 NE-$$-4329 RFR NO.4736 UPDATES FSAR SECTION E.3.1.4 TO REFLECT NRC APPROVED SEP,ARATION EXE RFR NO.4796 UPDATES THE FSAR SECTION 8.3.1.4.1.2 TO REFLECT NRC APPROYED EXEMP-TION FOR SIX INCH SEPARATION CRITERIA FOR THE WESTINGHOUSE SOLID STATE PROTEC-TION SYSTE9 LOGIC AND OUTPUT CASINETS, NUCLEAR INSTRUMENTATION SYSTEM CASINETS, AND THE 732J PROCESS C0hTROL SYSTEM CASINETS. THE BASIS FOR THE EXEMPTION WAS APPROVAL OF THE WESTINGHOUSE JUSTIFICATION PROVIDED IN WCAP 88924.
l PUASUANT TO THE A90VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN l
PR39A91LITY OF OCCURENCE OR CONSE2UENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATION $ IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSI61LITY F04 ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY CUESTIOu DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 122 LF-$o-JJ11 CN 88-J1,$P APP 9.59 REVISED FSAR SP FOR CLAREFICATION OF FIRE PROTECTION COM1.
CN dB-21,$P APP 9.53 REVISED THE FSAR SP FOR CLAREFICATION OF FIRE PROTECTION COMMITMENTS. CLAREFICATION RESULTED FROM AN ENGINEERING EVALUATION TO DETERMINE WHICH ROOMS ARE DESIGNATED AS PE RIPHER AL AND THUS REQUIRING AUTOMATIC SMOKE DETECTION AND SEPARATION FROM THE CONTROL R30M SY A ONE HOUR FIRE BARRIER.
PURSUANT TO THE AdOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEOUENCES OF AN ACCaDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETT OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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REPORT SAFETY EVALUATION ITEM ID 121 NE-35-4257 CMP 84-0434 ADDED BOUNDARY VALVES TO ESS. SERVICE WATER AND CONTAIN9ENT COOLING l
CMP 84-3434 ADDED BOUNDARY VALVES TO THE ESSENTIAL SERVICE WATER SYSTEM AND CONTAINMENT COOLING. LOCKED OPEN MANUAL ISOLATION VALVES WERE INSTALLED IN THE ESW PIPING TO AND FROM THE CONTAIhMENT AIR COOLERS. THE CHANGE FACILITATES CONTAINMENT PENETRATION ISOLATION VALVE TESTINGrAND EASIER MAINTENA1CE OF PENETRATION VALVES ANS ESW SYSTEM. THIS CHEhGE D000 NSi ALTER THE INTEGRITY OF THE ESSENTIAL SERVICE WATER SYSTEM OR LONTAINMENT PENETRATIONS INVOLVEDI BUT MAINTAINS REQUIRED HEAT REMOVAL FUNCTIONS. THESE SOUNDARY VALVES PROVIDE ONLY A PASSIVE SAFETY FUNCTION.
PURSUANT TO THE ASOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IM PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION Of EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MtLFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN CF SAFtTY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINE 3 THAT AN UNREVIEVED SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 122 NE-57-JJ43 OL 105S SusMITTED TECH SPEC CHANGES FOR INC# EASING CORE P0 DER LEVEL To 3565MWT OL 1058 SUBMITTED CHANGES TO SUPPORT INCREASING CORE POWER LEVEL TO 3565 MWT.
ENGINEERING AND LICENSING EVALUATIONS JUSTIFIED OPERATION AT THE UPRATED CONDI-TIONS.
THIS CHANGE WAS APPROVED BY THE NRC IN LICENSE AMENDMENT-35.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY A1ALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORTI OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL' SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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ITEM ID 125 1E-80-JJJ5 ETP-CE-ST3J1 PROCEDURE TESTED AN ANNUNCIATOR ALARM FOR GENERATOR ETP-CE-ST3J1 PROCEDURE TESTED AN ANNUNCIATOR WINDOW ADDED TO GIVE INFORMATION CONCEANING GENERATOR RUNSACK. THE TEST REOUIRED LIFTING LEADS TO ALARM THE CONTRGL ROOM ANNUNCIATOR. THE CIRCUITRY INVOLVED ANNUNCIATION ONLY.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBA91LITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY CVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-POET; OR CREATE POSSIBILI!Y FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN CF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNDEVIEWED SAFETY CUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM 20 12e NE-66-JJ1 TOPRP,REV 7 P*0CEDURE FOR TURBINE OVERSPEED PROTECTION RELIABILITY TOPRP,REV 7 880CEDURE FOR TURSINE OVERSPEED PROTECTION RELIABILITY WAS REVISED TO REQUIRE 1UARTERLY FREQUENCIES FOR TESTING MECHANICAL OVERSPEED TRIP,MECHANI-CAL TRIP PISTON, ELECTRICAL TRIP TEST, BACKUP OVERSPEED TRIP TEST,AND POWER LOAD IMBALANCE. THE SYSTEMS INVOLVED HAVE NO SAFETY DESIGN SASIS. FSAR A1ALYSES OF TUR8INE GENERATOR MISSILES REMAIN VALID. WITH THE REDUCTION OF FREQUENCIES OF TRIPS, WEAR ON THE OVERSPEED PROTECTION SYSTEM IS REDUCED. A QUARTERLY TEST FREQUENCY IS SUPPORTED aY THE PLANT'S EXPERIENCE OF No PROBLEMS WITH THE OVERSPEED PROTECTIOM SYSTEM FAILURE.
PURSUANT TO THE A30VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT! OR CREATE POSSIdILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY AN4 LYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNPEVIEWED SAFETY QUESTION DID NOT EXIST.
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13CFR50059 ANNUAL REPORT SUMMAREES r
0F UNION ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS
- EPORT SAFETY EVALUATION ITEM ID 127 NE-83-2013 9MP 88-2J2$ REPLACED CARBON STEEL PIPE WITH STAINLESS STEEL IN AF SYSTEM RMP ES-2BJ8 #EPLACED CARBON STEEL PIPE WITH STAINLESS STEEL PIPE IN THE FEED-WATER HEATER EXTRACTION AND DRAINS SYSTEM. THE MATERIAL CHANGE IS SUPERIOR AND A SOLUTION TO W4LL THINNING PR0aLEMS. CALCULATIONS CONFIRM THAT THE NEW PIPING DOES NOT PRESENT THERMAL STRESS CONCERNS. IN ADDITION, STAINLESS STEEL IS CLOSE TO CARBON STEEL IN RELATIVE ANODIC PROPERTIES, THUS RENDERING INSIGNIFICANT GALVANIC CORROSION SETWEEN THE TWO MATERIALS.
PURSUANT TO THE A90VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBASILITY OF OCCU4ENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTArdi TO SAFETY OVER PREVICUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTI OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A OIFFERENT TYPE OVER PREWIOUS EVALU4TIONS IN THE SAFETY ANALYSIS REPORTI OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE 8 ASIS FOR ANY TECHNICAL SPECIFICATION..
l THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY t
QUESTION DID NOT EXIST.
+
REPORT SAFETf EVALUATION ITEM IJ 128 NE-56-JJ14 CMP E7-1112 REROUTED CONDENSATE TO A CLEAN RADW4STE DRAIN HUB INSTEAD OF ASCRT CMP $7-1112 REROUTED THE CONDENSATE FROM THE HEATER VENT GAS COOLER AND STEAM TRAP,HF-ST-724,TO A CLEAN RADWASTE DRAIN HU3 TO PREVENT CONTAMINATION 0F THE AUX.STEA9 CONDENSATE RECOVERY TANKCASCRT). THE CHANGE WAS REQUIRED TO PREVENT CONTAMINATED CONDENSATE FROM ENTERING THE ASCRT. LESS THAN 2 GPM OF POTENTIALLY CONTAMINATED WATER IS REROUTED TO THE CRW DR41N SYSTEM. ALL ASSOCIATED PIPING MEETS THE STRESS REQUIREMENTS OF ANSI 331.1. POTENTIAL LEAKS FROM THIS PIPING IS CONTAINED WITHIN THE RADWASTE BUILDING. THE SECONDARY LIQUID WASTE SYSTEM IS NOT SAFETY-RELATED AND THIS DESIGN CHANGE DOES NOT IMPACT OPERATION OF SAFETY-RELATED EQUIPMENT.
PUR$UANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITT OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY A1ALYSIS RE-POATI OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT T!PE OVER PREVIOUS EVALUATIONS IN THE SAFETY AN4 LYSIS REPORTI OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
I THE EVALUATION DETERMIhED TH4T AN UNREVIEWED SAFETY QbESTIOM DID NOT EXIST.
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12CFR56.39 ANNUAL QEPORT SUMMARIES 05 UN10e ELECT 01C APPQ0VED WRITTEN SAFETY EVALUATIONS l
REPORT SAFETY EVALUATION 132 NE-83-JJ20 RFR NO.4857 REVISED FSAR FIG 13.2-1 FOR NEW COMPONENT ID FOR TURBI1E FRONT STD ITEM ID RFR NO.4859 REVISED FSAR FIS 13.2-1 FOR A NEWLY CREATED COMPONENT ID FOR THE MAIN TURBINE FRONT STARDARD. THE CHANGE INV3LVES DOCUMENTATION ONLY AND DOESN ALTER DESIGN 04 FUNCTION OF EQUIPMENF.
PURSUANT TO THE A30VE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITV 0F OCCURENCE 02 CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQ ME4T IMPO4T ANT TO S AFETY OVE A PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTJ OR CREATE POSSIBILITY FOR ACCIDENT OR MaLFUNCTIO4 0F A DIFFERENT TYPE OVER PREVI305 EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNdEVIEWED
- FETY GUESTION DID NOT EXIST.
REPORT SAFETY cVALUATION 133 NE-S3-JJ21 RFA NO.4747 REVISED FSAR FIG 2.2-5 FOR AS-sUILT, ACTUAL HYDROGEN GAS STORAGE,FLO ITEM IJ RFR NO.4797 REVISED FSAR FIG 2.2-5 FOR THE AS-0UILT, ACTUAL CONDITION OF THE HYD40 GEN GAS SYSTEM. THIS SYSTEM PROVIDES LOW PRESSURE GASEQUS 4YDROGEN TO THE TUR9INE-AND AUX. BUILDINGS FOR VOLUME CONTROL TAMK PURGE,FOR GENERATOR FILL AND LEA (AGE MAKEUP. THE CHANGE TO DOCUMENTATION DOES NOT ALTER DESIGN 04 FUNCTION OF THIS NONSAFETY-RELATED SYSTEM.
PURSUANT TO THE A90VE INFORMATION, THE CHLNGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR C04 SEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OWER PREVIOUS EVALUATIONS IN THE SAFETY A1ALYSIS RE-I PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE I
OVER PREVIOUS EVALUATIONS IN THE SAFETY ANLLYSIS REPORTJ OR REDUCE THE MAR =
GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATI01.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY OUESTIDW DID NOT EXIST.
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10CFR50.59 ANNUAL PEPORT SUMMARIES OF UNION ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 134 NE-33-JJ25 RFk NO.3555 REVISED FSAR FIG 13.4-6 FOR HEATER DRAIN TAN < tr"FL GAGE KOOT Ito.V RFR NO.3555 REVISED FSAR FIG 1J.4-6 FOR A CPANGE OF TF PS AT7NG POSITION OF ThE HEATER DRAIN TANK LEVEL gar,E ROOT I?~
THE PosI-J/IDE ISOLA-TION CHANGED FROM NORMALLY OPEN TO NORMALLY CLOSED.
s.
TION FOR THE HEATER DRAIN TANK LEVEL GAGE. THE CH ANr-TION DURING NORMAL GPERATION TO PREVENT LEAKAGE AND R ED'JCd PE R SO.
sHIS EQUIP-MENT IS NONSAFETY-RELATED.
PJRh2 ANT TO THE ASOV8 INFORMATION, THE CHANGE DOES NOT.. 0LVE AN INCREASE IN PR39ASILITY OF OCCURdNCE OR CONSEQUENCES OF AN ACCICENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT 03 MALFUNCTION OF A DIFFCRENT TfPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; 03 REDUCE THE MAR-GIN OF SAFF.TY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION.DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 135 LF-38-3033 CN 457 SP T3.11(9)-3 REVISED FSAR TO SHOW USE OF RAYCHEM HEAT SHRINK KITS CN 481 SP T3.11(B)-3 REVISED THE FSAR TABLE TO SHOW THE USE OF RAYCHEM HEAT SHRINK KITS IN SDECIFIED COMPONENT COOLING WATER SYSTEM AND CONTAIN9ENT PURGE
%YSTEM VALVES. THE 9AYCHEM KITS ARE CUALIFIED FOR USE ANYWHERE IN THE PLANT, INCLUDING INSIDE CONTAINMENT.
RAYCHEM HEAT SHRINK TUBING AND STUS CONNECTION KITS PROVIDE TERMINATIONS WHICH ARE SUPERIOR TO THE ORIGINAL SOLDER JOINTS.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION CF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFIhED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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19CFR50.59 ANNUAL REPORT SUMMQRIES OF UNION ELECYRIC APPROUE9 WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION 136 LF-$d-JJ34 CN 490 SP T3.11(8)-3 PROVIDED A GENERAL REVISION TO FSAR TA9LES 3.11,(03-3,-8 ITEM ID CN 490 SP T3.11(B)-3 PROVIDED A GENERAL REVISION TO FSAR TABLES 3.11(B)-3 AND 3.11(s)-8. THE REVISIONS UPDATE THESE TASLES TO MAKE THEM CONSISTENT BETWEEN THE CALLAWAY Q-LIST AND MASTER EQUIPMENT LISTS. ROOM AND EQUIPMENT LOCATIONS WERE VERIFIED; SOME EQUIPMENT WAS RECLASSIFIED FOR HARSH ENVIRONMENT; SOME I_
COMPONENTS JERE ADDED TO THE FSAR LIST; CATEGORIZATION CHANGES RESULTED IN ADDITIONAL EQ COMPONENTS LISTED; AND ANOTHER GENERIC REVISION INVOLVED LIST-ING APPURTENANCES ASSIGNED PLANT ID MUMSERS. ALL COMPONENTS THAT WERE ADDED WERE QUALIFIED AS OF NOVEM9ER 3J,1965, AND EQUIPMENT OPERASILITY CONCERNS WERE NOT GENERATED AS A RESULT OF THESE REVISIONS. THE CHANGES RENDER THE FSAR TABLES CONSISTENT WIT H PLANT DESIGN AND DO NOT IN ANY W AY DEGRADE PLANT SAFETY.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROBADILITY OF OCCURENCE OR CONSEQUENCES OF AtJ ACCIDENT OR MALFUNCTION OF EQUI MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIeILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFITY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UN 'CVIEW"D SAFETY QUESTION DID NOT EXIST.
REPORT SAFETY EVALUATION ITEM ID 137 NE-37-J1J7 CMP 84-0533 INSTALLED TWO 2-PEN TREND RECORDERS ON RADWASTE CONTROL ROOM PANELS CMP 84-0533 INSTALLED TWO 2-PEN TREND RECORDERS ON RADWASTE CONTROL ROOM PANELS HA134A,8. THE RECORDERS MONITOR H2 AND 02 INLET AND OUTLST CONCENTRATIONS FOR BOTH TRAINS OF THE HYDROGEN RECOMBINER SYSTEM. ALARM CONTACTS OF THE RECORDERS ARE WIRED TO LOCAL ANNUNCIATORS TO WARN OF CONCENTRATIONS EXCEEDING TECH SPEC LIMITS. SAFETY-RELATED SYSTEMS ARE NOT IMPACTED.
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PROOASILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE 34FETY ANALYSIS RE-PORT; 09 CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION ~0F A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; 01 REDUCE THE MAR-
. GIN OF SAFCTY AS DEFIN IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
.THE EVALUAT19N DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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10CFR50059 AMMUAL REPORT SUMMARIES OF UNION ELECTRIC APPROVED WRITTEN SAFETY EVALUATIONS REPORT SAFETY EVALUATION ITEM ID 133 NE-56-0J30 CN 88-08,SA 9.2.4.2 REVISED THE FSAR FOR MORE ACCURATE DESCRIPTION OF POTABLE S CN 88-0RsSA 9.2.4.2 REVISED THE FSAR FOR A MORE ACCURATE DESCRIPTION OF THE POTASLE WATER SYSTEM. CALLAJAY CURRENTLY USES A WELL AS THE PRIMARY SOURCE OF POTABLE WATER. THE ORIGINAL FSAR DESCRIPTION OF A BLEND OF DEMINERALIZED WATER AND FILTERED WATER I S N O L' THE SECONDARY SOURCE FOR THE PLANT. THE WELL WATER IS SUITABLE FOR POTABLE WATER AND IS CHLORINATED. BACKFLOW PREVENTERS ARE PROV-IDED. THIS WATER IS REQUIRED FOR OPERATION OF EMERGENCY EYE-WASH STATIONS AND THE WATER TREATMENT PLANT CHEMICAL FEED SYSTEM. IT IS NOT ESSENTIAL FOR SAFETY-RELATED SYSTEMS OR EQUIPMENT.
PdRSUANT TO THE A90VE INFORM ATION, THE CHANGE DOES NOT INVOLVE ~AN INCREASE IN PROBABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUfP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORTJ OR CREATE POSSI8ILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
I l'
REPORT SAFETY EVALUATION
?
ITEM ID 139 NO-83-0JJ1 CN 8 8-12 S A 12.5.2.1. 8 REVISED FSAR FOR METHODOLOGY FOR PERSONNEL DOSE CN 38-12 SA 12.5.2.1.8 WAS REVISED IN THE FSAR TO INCLUDE A CHANGE IN METHOD 0L-OGY FOR DETERMINING NEUTRON PERSONNEL DOSE AND FREQUENCY OF DOSE DETERMINATION.
THE REVISED METHODOLOGY DOES NOT ALTER FSAR ANALYSES. PERSONNEL DOSIMETRY DOES d
NOT IMPACT SAFETY-RELATED ITEMS.
PURSUANT TO THE ABOVE INFORMATIONr THE CHANGE DOES NOT INVOLVE AN INCREASE IN PR09 ABILITY OF OCCURENCE Ok CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIP-MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVIEWED SAFETY QUESTION DID NOT EXIST.
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12CFR50.59 ANNUAL REP 3RT SUMMARIES p
Of UNION ELECTRIC APPROUED WRITTEN SAFETY EVALUATIONS l
l f
REPORT SAFETY EVALUATION ITEM ID 140 OA-36-J044 CMP 64-0396 INSTALLED THE CONTAINMENT OREATHING AIR SYSTEM t
I CMP 84-0396 INSTALLED ThE CONTAINMENT BREATHING AIR SYSTEM.
THE INSTALLATION INCLUDED PIPING AND VALVES NEEDED TO MEET THE' CONTAINMENT
[
CRITERIA FOR ISOLATION. (THIS CHANGE IS FULLY IMPLEMENTED.)
PURSUANT TO THE ABOVE INFORMATION, THE CHANGE DOES NOT INVOLVE AN INCREASE IN PRODABILITY OF OCCURENCE OR CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQU 1
MENT IMPORTANT TO SAFETY OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS RE-PORT; OR CREATE POSSIBILITY FOR ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE l
OVER PREVIOUS EVALUATIONS IN THE SAFETY ANALYSIS REPORT; OR REDUCE THE MAR-GIN OF SAFETY AS DEFINED IN THE BASIS FOR ANY TECHNICAL SPECIFICATION.
THE EVALUATION DETERMINED THAT AN UNREVI"*>ED SAFETY QUESTION DID NOT EXIST.
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