Similar Documents at Perry |
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Category:ANNUAL OPERATING REPORT
MONTHYEARPY-CEI-NRR-2259, Plant,Jan-Dec 1997 Annual Rept to Nrc1997-12-31031 December 1997 Plant,Jan-Dec 1997 Annual Rept to Nrc ML20216G7611997-10-23023 October 1997 Safety Evaluation Summary,Per 10CFR50.59(B)(2) PY-CEI-NRR-2145, Jan-Dec 1996 Annual Rept1996-12-31031 December 1996 Jan-Dec 1996 Annual Rept PY-CEI-NRR-2024, Jan-Dec 1995 Annual Rept1995-12-31031 December 1995 Jan-Dec 1995 Annual Rept ML20081B7661994-12-31031 December 1994 Pnpp Safety Evaluation Summary Per 10CFR50.59(B)(2) PY-CEI-NRR-1918, NPP,940101-1231 Annual Rept1994-12-31031 December 1994 NPP,940101-1231 Annual Rept PY-CEI-NRR-1763, Jan-Dec 1993 Annual Rept. W/1993-12-31031 December 1993 Jan-Dec 1993 Annual Rept. W/ PY-CEI-NRR-1464, Annual Rept Jan-Dec 1991 Perry Nuclear Power Plant1991-12-31031 December 1991 Annual Rept Jan-Dec 1991 Perry Nuclear Power Plant ML20029B1871990-12-31031 December 1990 1990 Annual Rept. W/910228 Ltr ML20012A7141989-12-31031 December 1989 Jan-Dec 1989 Annual Rept. W/900228 Ltr ML20012C6511989-12-31031 December 1989 Safety Evaluation Summary,Per 10CFR50.59(b)(2) 1989. W/900313 Ltr PY-CEI-NRR-0970, Annual Rept for 19881988-12-31031 December 1988 Annual Rept for 1988 PY-CEI-NRR-0979, Safety Evaluation Summary Per 10CFR50.59(b)(2) 19881988-12-31031 December 1988 Safety Evaluation Summary Per 10CFR50.59(b)(2) 1988 ML20235G2681988-12-31031 December 1988 Annual ECCS Outage Rept,1988 PY-CEI-NRR-0820, Annual ECCS Outage Rept 19871987-12-31031 December 1987 Annual ECCS Outage Rept 1987 PY-CEI-NRR-0808, Clevland Electric Illuminating Co Perry Nuclear Power Plant,1987 Annual Operating Rept1987-12-31031 December 1987 Clevland Electric Illuminating Co Perry Nuclear Power Plant,1987 Annual Operating Rept PY-CEI-NRR-0596, Annual Rept to Nrc,Perry Nuclear Power Plant 860318-12311986-12-31031 December 1986 Annual Rept to Nrc,Perry Nuclear Power Plant 860318-1231 PY-CEI-NRR-0600, Annual ECCS Outage Rept,860318-12311986-12-31031 December 1986 Annual ECCS Outage Rept,860318-1231 1997-12-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & Pnpp QA Program ML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico PY-CEI-NRR-2437, Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With PY-CEI-NRR-2429, Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With PY-CEI-NRR-2424, Monthly Operating Rept for July 1999 for Perry Npp.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Perry Npp.With ML20210J3851999-07-28028 July 1999 Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval PY-CEI-NRR-2416, Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With ML20196A1951999-06-17017 June 1999 Instrument Drift Analysis ML20207G2741999-06-0707 June 1999 Safety Evaluation Concluding That Firstenergy Flaw Evaluation Meets Rules of ASME Code & That IGSCC & Thermal Fatigue Crack Growth Need Not Be Considered in Application PY-CEI-NRR-2409, Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2393, Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored1999-05-12012 May 1999 Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored ML20206G6451999-05-0303 May 1999 Safety Evaluation Authorizing Requests for Relief IR-032 to IR-035 & IR-037 to IR-040 Re Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp PY-CEI-NRR-2399, Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With ML20206E2261999-04-29029 April 1999 Safety Evaluation Concluding That Proposed Alternatives Will Result in Acceptable Level of Quality & Safety.Authorizes Use of Code Case N-504 for Weld Overlay Repair of FW Nozzle Weld at Pnpp & Use of Table IWB-3514 ML20206D7911999-04-23023 April 1999 Rev 6 to PDB-F0001, COLR for Pnpp Unit 1 Cycle 8,Reload 7 ML20205P4371999-04-15015 April 1999 Safety Evaluation Concluding That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves Susceptible to Pressure Locking or Thermal Binding ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20206D8461999-03-31031 March 1999 Rev 1 to J11-03371SRLR, Supplemental Reload Licensing Rept for Pnpp,Unit 1 Reload 7 Cycle 8 PY-CEI-NRR-2389, Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Perry Nuclear Power Plant,Unit 1.With ML20205G4221999-03-31031 March 1999 Safety Evaluation Accepting Second 10-yr Interval IST Program Releif Requests for Plant,Unit 1 ML20205D3101999-03-26026 March 1999 Safety Evaluation Supporting Amend 103 to License NPF-58 ML20205C3761999-03-26026 March 1999 Safety Evaluation Supporting Request for Proposed Exemption to 10CFR50,app a GDC 19 PY-CEI-NRR-2369, Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 9902271999-03-0303 March 1999 Special Rept:On 990127,PAMI Was Declared Inoperable.Caused by Low Resistance Reading Existing in Circuit That Goes to Drywell.Troubleshooting of Affected Cable Will Commence During RFO on 990227 PY-CEI-NRR-2372, Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Perry Nuclear Power Plant,Unit 1.With ML20203A5961999-02-0202 February 1999 Safety Evaluation Accepting Licensee Proposed Revs to Responsibilities of Plant Operations Review Committee as Described in Chapter 17.2 of USAR ML20203A5211999-01-27027 January 1999 Safety Evaluation Accepting Licensee Calculations Showing That Adequate NPSH Will Be Available for HPCS Pumps ML20198R8921999-01-0707 January 1999 SER Accepting Licensee Proposed Amend to TSs to Delete Reference to NRC Policy Re Plant Staff Working Hours & Require Administrative Controls to Limit Working Hours to Be Acceptable ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20206B0101998-12-31031 December 1998 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for Fiscal Yr Ending 981231,encl PY-CEI-NRR-2356, Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Perry Nuclear Power Plant,Unit 1.With ML20198J0031998-12-22022 December 1998 SER Accepting Licensee Response to GL 92-08,ampacity Derating Issues for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2346, Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Perry Nuclear Power Plant,Unit 1.With ML20195F6891998-11-0505 November 1998 Safety Evaluation Accepting Proposed Reduction in Commitment in Quality Assurance Program to Remove Radiological Assessor Position PY-CEI-NRR-2335, Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2329, Monthly Operating Rept for Sept 1998 for Perry Nuclear Power Plant,Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Perry Nuclear Power Plant,Unit 1.With ML20153B8221998-09-16016 September 1998 Safety Evaluation Accepting Changes to USAR Section 13.4.3, 17.2.1.3.2.2,17.2.1.3.2.2.3 & App 1A PY-CEI-NRR-2323, Monthly Operating Rept for Aug 1998 for Perry Nuclear Power Plant,Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Perry Nuclear Power Plant,Unit 1.With PY-CEI-NRR-2313, Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 11998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2306, Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Perry Nuclear Power Plant,Unit 1 ML20249A1891998-06-11011 June 1998 SER on Moderate Energy Line Pipe Break Criteria for Perry Nuclear Power Plant,Unit 1 & Requests Addl Info to Demonstrate That Plant & FSAR in Compliance W/Staff Position & GDC as Discussed in SER PY-CEI-NRR-2289, Monthly Operating Rept for May 1998 for Perry,Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Perry,Unit 1 ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted PY-CEI-NRR-2282, Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D2051998-04-20020 April 1998 SER Authorizing Licensee to Use Code Case N-524 Until Such Time as Code Case Included in Future Rev of RG 1.147 PY-CEI-NRR-2277, Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Perry Nuclear Power Plant,Unit 1 ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML20216G3901998-03-11011 March 1998 SER on Proposed Merger Between Duquesne Light Co & Allegheny Power Sys,Inc ML20216J1401998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Perry Nuclear Power Plant,Unit 1 PY-CEI-NRR-2258, Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 11998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Perry Nuclear Power Plant,Unit 1 1999-09-30
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GN75R90R
. ENERGY
. PERRY NUCLEAR POWER PLANT : Mail Address: Donald C. Shelton j
SENIOR VICE PRESIDENT 9O CENTER ROAD RRY,O 10 44081 NUCLEAR i
- PIRRY, OHIO 44061 1
-(216) 259-3737 February 28, 1995.
- PY-CEI/NRR-1918L United States Nuclear ReFulatory Commission Document Control Desk Washington, D.C. 20555 Perry Nuclear Power Plant Docket No. 50-440 1994 Annual Report Gentlemen Attached is the 1994 Annual Report for Perry Unit 1. This report is submitted in accordance with Technical Specifications 6.9.1.4 and 6.9.1.5 and fulfills ongoing commitments associated with Licensing Commitment 17 of USAR Appendix 1B.
If you have questions or require additional information, please contact Mr. James D. Kloosterman, Manager - Regulatory Affairs at (216) 280-5833.
Very t yours,
\
GMN:sc Attachment ces NRC Project Manager NRC Resident Inspector Office NRC Region III REIRS Project Manager 080026 1 9503090001 941231 PDR ADOCK 05000440 R PDR Operotng Compomes l[ g i
C% eland Electne timmmotmg Toleco f o son t j
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')- CLEVELAND ELECTRIC ILLUMINATING COMPANY-
' t PERRY NUCLEAR POVER PLANT ;
9 JANUARY 1 - DECEMBER 31, 1994 .
e ABBIUAL REPORT ,
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DOCKET NUMBER: 50-440- I LICENSE NUMBER: NPF-58 l t t
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Page 2 of 7
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' TABLE OF CONTENTS
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I. Occupational Exposure Summary Report. 3
'II. Safety / Relief Valve Challenges 5 ;
III. Reactor Coolant System Specific A'etivity Analysis '7 IV. Silicone Sealant Inspections- 7 6
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.I.; Occupational Radiation Exposure Summary Report. .
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t.p c Enclosed in this section is the-1994 Annual Occupational. Exposure Summary - ~
grouped ~as' indicated below: s i
' STATION: Perry' Nuclear Power l Plant Department, Site Protection Section-of the Perry Nuclear Services Department' UTILITY Perry Nuclear' Assurance' Department, Perry Nuclear Engineering ,
Department, other Sections of the Perry Nuclear. Services l Department, and CEI support personnel- ; ;
'l OTHER Contractor, Consultant,~Centerior, Davis-Besse, and other !
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1994 A ZUAL EXPOSU23 REP 3RT' QBSULAT32T SUIDE 1.16 APP 20912 A
SUMMARY
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REACTOR OPER. & SURVEILLANCE' MAINTENANCE 132 63~ 502 1.090' O.045- 9.111 r OPERATIONS 278 39 10 '23.211 1.026 '0.771' '
NEALTN PNYSICS 58 23 213 7.618 1.184 26.650' SUPERVISORY 3 2 34 0.034 0 0072 0.279 ENGINEERING 8 141 66 0.269 1.272 0.722' ROUTINE MAINTENANCE MAINTENANCE 179- 127 1510 23.544 6.716' 255.244-OPERATIONS ~ 308 47 32 8.832' O.330 1.089 NEALTN PNYSICS 61 26 246 4.633 0.710 .18.144 SUPERVISORY 4 3 64 0.005 0.000 0.483 ENGINEERING 19 226 211- 0.275 7.356 18.593 INSERVICE INSPECTION ' MAINTENANCE 59 10 701 0.400 0.271 46.431 OPERATIONS 62 6 7 1.199 '0.140 0.160 NEALTN PHYSICS 15 4 68 0.267 0.058 1.092 SUPERVISORY 0 0 7 0.000 0.000 0.102 ENGINEERING 4 60 73 0.157 2.412 9.608
-SPECIAL MAINTENANCE MAINTENANCE 110 46 785 '5.385 0.120 67.185-OPERATIONS 103 4 5 1.860 0.027 0.096 NEALTN PNYSICS 30 8 97 1.290 0.084 -2.745 SUPERVISORY 1 0 2 0.000 0.000 0.004 ENGINEERING 5 61 59 0.024 '1.911 1.938 WASTE PROCESSING MAINTENANCE 105 58 370 0.068 4.563 4.749-OPERATIONS 70 9 3 3.325 0.009 0.010 NEALTN PNTSICS 48 19 166 2.491 1.791 3.554-SUPERVISORT 0 1 '2 0.000 0.000 0.000 ENGINEERING 2 24 4 0.005 0.085- 0.015' REFUELING MAINTENANCE 96 51 690 19.386 1.204 68.225 OPERATIONS 133 9 8 21.369 2.540 0.604 NEALTN PNTSICS 29 19- 144 -1.201 0.377 6.893 SUPERVISORY 1 0 2 0.002 0.000 0.032 ENGINEERING 6 76 35 0'647
. 4.655 1.238 TOTALS MAINTENANCE 681 355 4558 49.873 12.959 450.949-OPERATIONS 954 114 65 59.796 -4.112 '2.730 NEALTH PHYSICS 241 '99 934 17.500 4.204 59.078 SUPERVISORY 9 6 111 0.041 0.007- 0.900
. ENGINEERING 44. 544 448 1.377 17.691 32.114-GRAND TOTALS 1929 1162 6116 128.587 38.973 545.771 Wete:
MAN-REM is based on Direct Reading Domineter Readings.
4 Persons is based on number of unique individuals signing in on any RWP in corresponding categories:
regardless of exposure received. . gf )l f _
' 88 I a work Category is based on RWP Individual signed in on.
Job Category and Station / Utility /Other is based on personnel record of individual signing in on corresponding RWP.
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'II.. SAFETT/ RELIEF VALVE CHALLENGES The attached report; includes all actuations during the 1994 year.
-During Refuel Outage #4 alllthe SRVs were removed and replaced with
-refurbished valves. Prior to declaring the newly installed valves operable, per Technical Specifications 4.0.5, each valve was tested asi required by SVI B21-T2005, "SRV Exercise Test."
On February 25 and 26, two SRVs, 1B21-F051C and 1821-F051D, were' unexpectedly opened. Each valve was actuated four times._ The plant was shutdown for Refuel' Outage #4.. Licensee' Event Report (LER)'94-008'rev. O was submitted to the NRC_as a voluntary report.
This information is submitted :ba accordance with Technical Specification .
6.9.1.5.b of Appendix A to Operating License NPF-58 for the Perry Nuclear Power Plant, Unit 1.
1 Included as an SRV " challenge" are the following actions / events. ,
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- 1. .The SRV being physically' operated by the manual control switch in the Control room.
- 2. The SRV automatically: lifts per design pressure limit when installed '
in the plant.
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SAFETY / RELIEF ACTUATIONS DURING'1994=
DATE-2/25/94 & 2/26/94 DATE-7/25/94 & 7/26/3 if VALVE NUMBER. VALVE NUMBER 1B21-F041A 1B21-F041B 1B21-F041C* 1B21-F041D:
1B21-F041E 1821-F041F 1B21-F041G 1B21-F041K.
1B21-F047B 1B21-F047D 1B21-F047F* IB21-F047G
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1B21-F047Hs 1B21-F051A 1 21-F051B 1B21-F051C**
IB21-F051D** IB21-F051G 1B21-F047C
'*These two' valves were actuated three times during the test,~all'other' valves were actuated twice.
- These two valves were both actuated unexpectedly cni 2/25 for11B21-F051C and.
1 2/26 for IB21-r051D. .The number of actuations for each. valve ~vas four,;
-a total of eight actuations.
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..III(Reactor Coolant System Specific Activity JAnalysis-I d :During 1994 there were no' occurrences:in which Technical Specificath n 3.4.5,." Specific Activity",, Limiting Condition for Operation was.,...
exceeded. This information is' submitted in accordance with1 Technical
, -Specification 6.9.1.5.c.:
IV. Silicone Sealant I'nspections-In~accordance.vith' commitments made in response.to License Commitment 17 of the USAR' Appendix 1B (reference letter.PY-CEI/NRR-0703L dated August 27, 1987 from Murray R. Edelman)lthe following summary report lis provided. -During the Perry Unit 1, fourth refueling outage.(February 5,.
1994 - August 14, 1994)-duct specimens that were previously placed inian-environmentally representative horizontal pipe chase-in the Intermediate
. Building, 585'. elevation vere inspected. The du't e specimens'. vere. leak tested at rated pressure, with acceptable-results.- Thelresults of the duct specimen-leak test showed.that no additional air leakage'vastpresent' than previously identified in the original; test.
A valkdown of representative ~ portions:of Engineered' Safety Feature (ESP).
ventilation systems [ Annulus: Exhaust Gas Treatment (M15) . Control ~ Room-HVAC (M25) and Fuel Handling Building. Ventilation-(M40)]'was conducted and the exposed exterior silicone sealants were inspected, also with-acceptable results- .
..