Similar Documents at Surry |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML18152B3371999-09-24024 September 1999 SER Accepting Third 10-year Interval Inservice Insp Plan Request for Relief SR-026 for Surry Power Station Unit 2 ML18152B3631999-08-23023 August 1999 Safety Evaluation Supporting Eddy Current Techniques Used by VEPCO to Determine Depth of Degradation Evident in Units SG Tubing & VEPCO Approach for Dispositioning Tubes with Avb Wear Indications ML18152B3831999-08-23023 August 1999 Safety Evaluation Granting Relief Request from ASME Section XI Requirements for Containment Insp ML18152B3841999-08-23023 August 1999 Safety Evaluation Granting Relief Request from ASME Section Xa Requirements for Containment Insp ML20196J4781999-07-0101 July 1999 Safety Evaluation Supporting Amends 221 & 221 to Licenses DPR-32 & DPR-37,respectively ML20195D3571999-06-0707 June 1999 Safety Evaluation Supporting Amends 220 & 220 to Licenses DPR-32 & DPR-37,respectively ML18152B6481999-04-14014 April 1999 Safety Evaluation Supporting Relief Requests IWE-2,4.5.6 & IWL-2 to Licenses DPR-32 & DPR-37 Respectively ML18152B6451999-04-13013 April 1999 SER Accepting Util Reactor Pressure Vessel Fluence Methodology for Surry Power Stations,Units 1 & 2 & North Anna Power Station,Units 1 & 2 Subject to Listed Limitations ML20207L8081999-03-12012 March 1999 Safety Evaluation Supporting Amends 219 & 219 to Licenses DPR-32 & DPR-37 ML18152B5381999-02-16016 February 1999 SER Accepting Third 10-year Interval Inservice Insp Request for Relief for Surry Power Station,Unit 1.Staff Concludes That Licensee Proposed Alternative Will Provide Acceptable Level of Quality & Safety.Technical Ltr Rept Also Encl ML18152B5861998-12-18018 December 1998 SER Approving Request Relief Related to Inservice Testing Program at Surry Power Station Unit 1 ML18152B5901998-12-16016 December 1998 Safety Evaluation Authorizing Request to Use Code Case N-577 as Alternative to Requirements of ASME Code Section XI for Surry Power Station,Unit 1 ML20198F9221998-12-16016 December 1998 Safety Evaluation Supporting Amends 217 & 217 to Licenses DPR-32 & DPR-37,respectively ML20151U7261998-09-0303 September 1998 Safety Evaluation Approving Exemption from Certain 10CFR20 Requirements Re Use of self-contained Breathing Apparatus with Enriched Oxygen in Subatmospheric Containments at SPS ML20237E9721998-08-26026 August 1998 Safety Evaluation Supporting Amends 216 & 216 to Licenses DPR-32 & DPR-37,respectively ML20236R2111998-07-15015 July 1998 SER Related to Request for Revised Exemption from 10CFR70.24(a) for Surry Power Station,Units 1 & 2 ML20249B8191998-06-19019 June 1998 Safety Evaluation Supporting Amends 215 & 215 to Licenses DPR-32 & DPR-37,respectively ML20249B8261998-06-19019 June 1998 Safety Evaluation Supporting Amends 214 & 214 to Licenses DPR-32 & DPR-37,respectively ML20248M0911998-06-11011 June 1998 Safety Evaluation Supporting Amends 213 & 213 to Licenses DPR-32 & DPR-37,respectively ML18152B8011998-05-0404 May 1998 Safety Evaluation Granting Third 10-year Interval Inservice Insp Plan Request for Relief SR-19 for Surry Power Station, Unit 1 ML18152B7881998-04-28028 April 1998 SER Accepting Request for Relief from ASME Code Requirements - Deferral of Repair to RHR Sys Piping ML18153A3011998-04-20020 April 1998 Safety Evaluation Denying Licensee Assessment of Reactor Vessel Structural Integrity ML20217P9941998-04-0707 April 1998 Safety Evaluation Granting Licensee Third 10-yr Inservice Insp Program Relief Requests SR-018 - Sr-024 ML18153A3841997-12-0303 December 1997 Safety Evaluation Accepting Licensee Structural Integrity & Operability Assessments ML20202B8751997-11-24024 November 1997 Safety Evaluation Denying Licensee Request for Exemption from Section III.G.2.f of App R to 10CFR50.Staff Concluded That Use of Combustible Radiant Energy Heat Shields Inside Containment at Surry & North Anna Unacceptable ML18153A4011997-11-24024 November 1997 Safety Evaluation Accepting Licensee Proposed Alternative to Perform Visual Exam of Reactor Vessel Closure Head Nuts in Lieu of Surface Exam ML18153A4471997-10-0101 October 1997 Safety Evaluation Re Relief from Implementation of 10CFR50.55a Requirements for Surry Power Station,Units 1 & 2 & North Anna Power Station,Units 1 & 2 ML20217P0951997-08-21021 August 1997 Safety Evaluation Accepting Licensee ,As Suppl by 970324 Request for Exemption from Requirements of 10CFR70.24(a) Re Criticality Monitors as Pertaining to Unirradiated Fuel & Other Forms of Special Nuclear Matls ML20149D8361997-07-15015 July 1997 Safety Evaluation Supporting Amends 211 & 211 to Licenses DPR-32 & DPR-37,respectively ML18153A1271997-04-11011 April 1997 Safety Evaluation Accepting Third 10-yr ISI Interval Requests for Relief Sr-14 - SR-17 for Plant,Unit 2 ML18153A0511996-08-30030 August 1996 SE Granting Third 10-yr Interval ISI Program Plan Requests for Relief SR-009 Through SR-017,subj to Requirement for Relief Request SR-014 ML20117M4281996-06-0707 June 1996 Safety Evaluation Supporting Amends 210 & 210 to Licenses DPR-32 & DPR-37 ML20108B3661996-04-29029 April 1996 Safety Evaluation Supporting Amends 209 & 209 to Licenses DPR-32 & DPR-37,respectively ML20107K0081996-04-18018 April 1996 Safety Evaluation Supporting Amends 208 & 208 to Licenses DPR-32 & DPR-37,respectively ML18153A6091996-04-16016 April 1996 Safety Evaluation Authorizing Third 10-yr Interval ISI Program Plan Requests for Relief to Use Code Cases N-522 & N-535 at Plant,Per 10CFR50.55a(a)(3)(i) ML20099M0071995-12-28028 December 1995 Safety Evaluation Supporting Amends 207 & 207 to Licenses DPR-32 & DPR-37,respectively ML18153A5631995-12-19019 December 1995 SER Recommending That Relief Requests SR-22 Through SR-26, Be Granted,Per 10CFR50.55a(g)(6)(i) ML18153A5541995-12-13013 December 1995 Safety Evaluation Accepting Change to Emergency Plan Augmentation Goals of Selected Responders from 30 Minutes to 45 Minutes for Plant ML20092G7381995-09-14014 September 1995 Safety Evaluation Supporting Amends 205 & 205 to Licenses DPR-32 & DPR-37 ML20092A3131995-09-0101 September 1995 Safety Evaluation Supporting Amend 204 to Licenses DPR-32 & DPR-37 ML18153A7511995-08-30030 August 1995 Safety Evaluation Granting Third 10-yr Interval Inservice Insp Program Plan,Rev 0 & Associated Requests for Relief ML20087B5731995-08-0303 August 1995 Safety Evaluation Supporting Amends 203 & 203 to Licenses DPR-32 & DPR-37,respectively ML20087A1791995-07-27027 July 1995 Safety Evaluation Supporting Amends 202 & 202 to Licenses DPR-32 & DPR-37,respectively ML18153A7261995-07-19019 July 1995 Safety Evaluation Re Third 10-yr Interval Inservice Insp Program Update & Associated Requests for Relief ML18153A7101995-07-19019 July 1995 Safety Evaluation Granting Requests for Relief RR-2,RR-6, RR-7,RR-8,RR-11,SR-002,SR-003,SR-004 & SR-006 ML20086J7611995-07-11011 July 1995 Safety Evaluation Supporting Amends 201 & 201 to Licenses DPR-32 & DPR-37,respectively ML18153A6951995-07-0606 July 1995 SER Denying Proposed Revisions to Decrease Effectiveness of Currently Approved Emergency Plan for Each Site ML20086E3221995-06-29029 June 1995 Safety Evaluation Supporting Amends 200 & 200 to Licenses DPR-32 & DPR-37,respectively ML18153A8511995-06-0808 June 1995 Safety Evaluation Granting Third Interval Inservice Insp Program Relief Requests from ASME Code Section XI for Plant, Unit 1 & 2 ML20091R3121995-05-31031 May 1995 Safety Evaluation Supporting Amend 199 to Licenses DPR-32 & DPR-37,respectively 1999-09-24
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619 05000281/LER-1999-004-02, :on 981109,EDG Was Inoperable Longer than Allowed by TS Due to Governor Compensation Valve.Root Cause Evaluation Being Performed to Determine How Compensation Valve Became Closed1999-10-0101 October 1999
- on 981109,EDG Was Inoperable Longer than Allowed by TS Due to Governor Compensation Valve.Root Cause Evaluation Being Performed to Determine How Compensation Valve Became Closed
ML18152B3531999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With ML18152B3371999-09-24024 September 1999 SER Accepting Third 10-year Interval Inservice Insp Plan Request for Relief SR-026 for Surry Power Station Unit 2 ML18152B6651999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 05000280/LER-1999-006, :on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With1999-08-27027 August 1999
- on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With
05000280/LER-1999-005-01, :on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed1999-08-27027 August 1999
- on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed
ML18152B3841999-08-23023 August 1999 Safety Evaluation Granting Relief Request from ASME Section Xa Requirements for Containment Insp ML18152B3631999-08-23023 August 1999 Safety Evaluation Supporting Eddy Current Techniques Used by VEPCO to Determine Depth of Degradation Evident in Units SG Tubing & VEPCO Approach for Dispositioning Tubes with Avb Wear Indications ML18152B3831999-08-23023 August 1999 Safety Evaluation Granting Relief Request from ASME Section XI Requirements for Containment Insp 05000280/LER-1999-004-01, :on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms1999-08-13013 August 1999
- on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms
ML18151A3981999-08-13013 August 1999 SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage ML18152B3791999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 05000281/LER-1999-003-02, :on 990705,auto Reactor Trip on Low Coolant Flow,Occurred.Caused by Loop Stop Valve Failure.Approved RCE Recommendations,Designed to Prevent Recurrence of Similar Event Will Be Implemented Through CAP1999-07-30030 July 1999
- on 990705,auto Reactor Trip on Low Coolant Flow,Occurred.Caused by Loop Stop Valve Failure.Approved RCE Recommendations,Designed to Prevent Recurrence of Similar Event Will Be Implemented Through CAP
ML20196J4781999-07-0101 July 1999 Safety Evaluation Supporting Amends 221 & 221 to Licenses DPR-32 & DPR-37,respectively ML18152B3911999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With ML20195D3571999-06-0707 June 1999 Safety Evaluation Supporting Amends 220 & 220 to Licenses DPR-32 & DPR-37,respectively ML20195E2401999-05-31031 May 1999 Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag ML18152B4341999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 05000281/LER-1999-002-02, :on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With1999-05-18018 May 1999
- on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With
ML18152B4161999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With 05000280/LER-1999-003-01, :on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With1999-04-28028 April 1999
- on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With
ML18152B6481999-04-14014 April 1999 Safety Evaluation Supporting Relief Requests IWE-2,4.5.6 & IWL-2 to Licenses DPR-32 & DPR-37 Respectively ML18152B6451999-04-13013 April 1999 SER Accepting Util Reactor Pressure Vessel Fluence Methodology for Surry Power Stations,Units 1 & 2 & North Anna Power Station,Units 1 & 2 Subject to Listed Limitations 05000281/LER-1999-001-02, :on 990301,RPS Relay Not Placed in Trip Resulted in Violation of TS 3.7.Caused by Lack of Procedural Guidance.Developed New Procedure to Provide More Explicit Instructions for Placing Stop Valve in Relay Trip1999-03-31031 March 1999
- on 990301,RPS Relay Not Placed in Trip Resulted in Violation of TS 3.7.Caused by Lack of Procedural Guidance.Developed New Procedure to Provide More Explicit Instructions for Placing Stop Valve in Relay Trip
ML18152B6511999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2 05000280/LER-1999-002-01, :on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 9902121999-03-29029 March 1999
- on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212
05000280/LER-1998-013, :on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr1999-03-19019 March 1999
- on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr
ML20207L8081999-03-12012 March 1999 Safety Evaluation Supporting Amends 219 & 219 to Licenses DPR-32 & DPR-37 ML18152B7331999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With ML18152B5381999-02-16016 February 1999 SER Accepting Third 10-year Interval Inservice Insp Request for Relief for Surry Power Station,Unit 1.Staff Concludes That Licensee Proposed Alternative Will Provide Acceptable Level of Quality & Safety.Technical Ltr Rept Also Encl ML18152B5421999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Surry Power Station,Units 1 & 2.With ML18151A3031999-01-29029 January 1999 ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements 05000280/LER-1999-001, :on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable1999-01-21021 January 1999
- on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable
ML18152B6011998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Surry Power Station,Units 1 & 2.With ML18152B5861998-12-18018 December 1998 SER Approving Request Relief Related to Inservice Testing Program at Surry Power Station Unit 1 ML20198F9221998-12-16016 December 1998 Safety Evaluation Supporting Amends 217 & 217 to Licenses DPR-32 & DPR-37,respectively 05000280/LER-1998-014, :on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition1998-12-16016 December 1998
- on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B5901998-12-16016 December 1998 Safety Evaluation Authorizing Request to Use Code Case N-577 as Alternative to Requirements of ASME Code Section XI for Surry Power Station,Unit 1 ML18152B7121998-12-0404 December 1998 LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened 05000280/LER-1998-012, :on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With1998-12-0101 December 1998
- on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With
ML18152B7081998-11-30030 November 1998 Rev 0 to COLR for Surry 1 Cycle 16,Pattern Un ML18152B5721998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Surry Power Station,Units 1 & 2.With ML18152B6241998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Surry Power Station Units 1 & 2.With ML18152B6881998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Surry Power Station Units 1 & 2.With ML20151U7261998-09-0303 September 1998 Safety Evaluation Approving Exemption from Certain 10CFR20 Requirements Re Use of self-contained Breathing Apparatus with Enriched Oxygen in Subatmospheric Containments at SPS ML18153A3271998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Surry Power Station,Units 1 & 2 ML20237E9721998-08-26026 August 1998 Safety Evaluation Supporting Amends 216 & 216 to Licenses DPR-32 & DPR-37,respectively ML18153A3161998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Surry Power Station Units 1 & 2 05000280/LER-1998-010, :on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status1998-07-31031 July 1998
- on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status
1999-09-30
[Table view] |
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' UNITED STATES i
{
'j-NUCLEAR REGULATORY COMMISSION o
e WASHINGTON, D.C. 206 5 0001
.....l SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
(.
RELATED TO AMENDMENT NO. 220 TO FACILITY OPERATING LICENSE NO. DPR-32
' AND AMENDMENT NO; 220 TO FACILITY OPERATING LICENSE NO. DPR-37
\\
. VIRGINIA ELECTRIC AND POWER COMPANY SURRY' POWER STATION. UNIT NOS.1 ANQ2 s
DOCKET NOS. 50-280 AND 50-281 l
1.0 INTRODUCTION
By letter dated February 16,' 1999, the licensee proposed editorial changes to the plant Technical Specifications (TS) to consolidate the auxiliary feedwater (AFW) cross-connect i
requirements by relocating the associated electrical power requirements. Also, the licensee proposed additional editorial changes to various TS.
2.0 EVALUATION The licensee proposed the following specific changes to the plant TS:
j i
Change 1: In TS 3.6.B delete "1. The following shall be operable:" and substitute "The following shall apply;" at the end of the first paragraph.
Since the proposed individual specifications in TS 3.6.B contain their respective requirements for operability / availability, this proposed change is considered editorial in nature and is therefore acceptable on that basis.
Chance 2: Delete TS 3.6.B.1.a and substitute "1. Two motor driven auxiliary feedwater pumps shall be OPERABLE."
l This proposed change, coupled with Change 1 above, relocates the operability requirement from the opening paragraph in TS 3.6.B to this individual specification. The change is considered editorial and is therefore considered acceptable on that basis.
Change 3: Add a new TS 3.6.B.4 with "The auxiliary feedwater cross-connect capability shall be available, as follows:" as the first sentence.
l i
Enclosure f
9906090129 990607 ADOCK 0 Q b
PDR
u 3.
... Chanoe'3A: Delete the existing TS 3.6.B.1.b and substitute:
'Two of the three auxiliary feedwater pumps on the opposite unit (automatic initiation instrumentation need not be OPERABLE) capable of being used with the opening of the cross-connect.
as new TS 3.6.B.4.a.
Chance 38: Delete the last sentence from the existing TS 3.6.B.2 and substitute:
A minimum of 60,000 gallons of water available in the protected condensate storage tank of the opposite unit to supply emergency water to the auxiliary feedwater pump suction of that unit.
as new TS 3.6.B.4.b.
Chance 3C: Delete existing TS 3.16.A.8 and substitute the following as new TS 3.6.B.4.c:
c.
Emergency power supplied to the opposite unit's auxiliary feedwater pumps and to the AFW cross-connect valves, as follows:
- 1.. Two diesel generators (the opposite unit's diesel generator and the shared backup diesel generator) OPERABLE with each generator's day tank having at least 290 gallons of fuel and with a minimum on-site supply of 35,000 gallons of fuel available.
2.
Two 4160V emergency buses energized.
i 3.
Two OPERABLE flow paths for providing fuel to the opposite unit's diesel generator and the shared backup diesel generator.
4.
Two station batteries, two chargers and the DC distribution systems OPERABLE.
- 5. ' Emergency diesel generator battery, charger and the DC control circuitry OPERABLE for the opposite unit's diesel generator and for the shared backup diesel generator.
6.
The 480V emergency buses energized which supply power to the auxiliary feedwater cross-connect valves:
a.
For AFW from Unit 1 to Unit 2: Buses 1H1 and 1J1.
b.
For AFW from Unit 2 to Unit 1: Buses 2H1 and 2J1.
I
-{
4 4- )
i
- 7. _ One of the two physically independent circuits'from the offsite transmission network energizing the opposite unit's emergency buses.
i These proposed changes relocate and consolidate the existing AFW cross-connect requirements and are editorial in nature. On this basis they are therefore considered acceptable.
Chance 4:
In TS 3.6.D delete "3.6.B.1,3.6.B.2,3.6.B.3," and substitute "3.6.B".
i This proposed change moves the TS reference up one level and is editorial in nature. On this basis it is therefore considered acceptable.
Chance 5:
In TS 3.6.G delete "3.6.B.1,3.6.B.2" and substitute "3.6.B". Also delete the comma following "and" and before "the protected" in the first sentence.
The first proposed change moves the TS reference up one level. Both changes are editorial in nature and are therefore acceptable on that basis.
Chanae 6:.
Delete existing TS 3.16.B.4 and substitute the following as new TS 3.6.G.3:
c.
A train of the opposite unit's emergency power system as required by
{
Section 3.6.B.4.c above may be inoperable for a period not to exceed 14 j
days; if this train's inoperability is related to a diesel fuel oil path, one diesel fuel oil path may be " inoperable" for 24 hours provided the other flow path is proven OPERABLE; if after 24 hours; the inoperable flow path cannot be restored to service, the diesel shall be considered j
" inoperable". During this 14 day period, the following limitations apply:
I i
a.
If the offsite power source becomes unable to energize the opposite unit's OPERABLE train, operation may continue provided its associated emergency diesel generator is energizing the j
OPERABLE train.
b.
If the opposite unit's OPERABLE train's emergency diesel generator becomes unavailable, operation may continue for 72 hours provided the offsite power source is' energizing the opposite unit's OPERABLE j
train.
i
- c.
Return of tim originally inoperable train to OPERABLE status allows the second inoperab!c train to revert to the 14 day limitation.
2
[_
]
.4 L>
' This change relocates and consolidates the action statements for the AFW cross-connect electrical power. In addition, the action requirements for the diesel fuel oil path inoperability,
. identical to existing TS 3.16.B.1.b, have been included. These changes are editorial in nature L
~ and are therefore considered acceptable.
Chance 7:
In the second paragraph of the Basis for TS 3.6, start a new paragraph with the j
l' third sentence. Add "In addition," following the last sentence of this new
]
paragraph and append the last paragraph on Page TS 3.16-6 from the Basis for 1
TS 3.16. Add the following to replace the paragraph removed from the Basis for
.)
TS 3.16.
1
- The electrical power requirements and the emergency power testing requirements for the AFW cross-connect are contained in TS 3.6.B.4.c and TS 4.6, respectively.
i This change relocates and consolidates the Basis discussion for the AFW cross-connect requirements. This change is' editorial in nature and is therefore considered acceptable.
Chance 8:
Delete TS 3.9.B.-
Since the AFW cross-connect electrical power requirements are being relocated and consolidated in TS 3.6 (as proposed in the above changes), this change eliminates unnecessary electrical power requirements which are contained in the revised TS 3.6 and is editorial in nature. On that basis it is considered acceptable.-
i Chance 9:
Delete TS 3.9.C. Also combine the first and second paragraphs under the Basis j
for TS 3.9 and delete the last sentence.
This change eliminates the electrical power requirements and the corresponding Basis
- discussion associated with power operation with less than three loops in service. This material is no longer necessary since power operation with less than three loops in service is prohibited.
This change is editorial in nature and is there considered acceptable.
^
Chance 10:
Existing TS 3.9.D is renumbered 3.9.B.
This change results from Changes 8 and 9 above and is editorial in nature. On that basis it is considered acceptable.
l Chance 11: ' Delete the existing last paragraph under the Basis for TS 3.9 and substitute:
The electrical power requirements and the emergency power testing requirements for the auxiliary feedwater cross-connect are contained in TS
- 3.6.B.4.c and TS 4.6, respectively.
This change _is part of the consolidation of the Basis discussion for the AFW cross-connect requirements to the Basis under TS 3.6. It is editorial in nature and is therefore considered acceptable.-
~
., l Chance 12:
In TS 3.6.A replace " operable" with " OPERABLE". In TS 3.6.F replace
)
" operable" with " OPERABLE" and " hot shutdown" with " HOT SHUTDOWN". In the last sentence of TS 3.6.G, replace " hot shutdown" with " HOT SHUTDOWN" l
and " cold shutdown" with " COLD SHUTDOWN". In TS 3.9.A.7 replace
" operable" with " OPERABLE." In TS 3.16.A.1 replace " operable" with
" OPERABLE". In TS 3.16. A.5,6, and 7 replace " operable" with " OPERABLE".
In TS 3.16.B replace " hot shutdown conditions" with " HOT SHUTDOWN". In TS 3.16.B.1.a.2 replace " operable" with " OPERABLE" in two places. In TS 3.16.B.1.a.3 replace " operable" with " OPERABLE", " hot shutdown" with " HOT SHUTDOWN", and " cold shutdown" with " COLD SHUTDOWN". In TS 3.16.B.1.b replace " operable" with " OPERABLE". In TS 3.16.B.2 replace
" operable" with " OPERABLE" and "the cold shutdown condition" with " COLD,
SHUTDOWN". In TS 3.16 B.3 replace " operable" with " OPERABLE" in three places, "the hot shutdown condition" with " HOT SHUTDOWN", and "the cold shutdown condition" with " COLD SHUTDOWN".
These changes are all editorial in nature and are taerefore acceptable.
Channe 13:
Revise TS 3.16.A.4 as follows adding the parenthesis and a previously omitted i
"V."
Two physica!!y independent circuits from the offsite transmission network to energize the 4160V and 480V emergency buses. One of these sources must be immediately available, (i.e. primary source) and the other must be capable of bein.g made available within 8 hours, (i.e. dependable alternate source).
This change is editorial and is therefore acceptable.
Chance 14:
In TS 3.16.B.1.b add " path" after " flow" in the second line.
This is an editorial change and is therefore acceptable.
Chanae 15:
In the second sentence of TS 3.16.B.3, insert a comma after " period".
This change is editorial and is therefore acceptable.
3.0 STATE CONSULTATION
in accordance with the Commission's regulations, the Virginia State official was notified of the proposed issuance of the amendments. The State official had no comment.
4.0 ENVIRONMENTAL CONSIDERATION
These amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes a sunroillance requirernent. The NRC staff has determined that the amendments involve no significant increase in the amoda.ts and no significant change in the types of any effluents that may be released offsite, and that there is no significant increase'in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding l
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. l that these amendments involve no significant hazards consideration and there has been no public comment on such finding (64 FR 24203). Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR
-51.22(b) no environmental impact. statement or environmental assessment need be prepared in connection with the issuance of these amendments.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by 2 operation in the proposed manner, (2) such activities will be conducted in compliance with the
- Commission's regulations, and (3) the issuance of these amendments will not be inimical to the common defense and security cr to the health and safety of the public.
Principal Contributor: F. Burrows
' Date: - June 7,1999 i
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DATED:
June 7,1999 l
AMENDMENT NO. 220 TO FACILITY OPERATING LICENSE NO. DPR SURRY UNIT 1 l
AMENDMENT NO. 220 TO FACILITY OPERATING LICENSE NO. DPR SURRY UNIT 2 l
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H. Berkow E. Dunnington G. Edison OGC
- G. Hill (4), TWFN, 5/C/3 W. Beckner F. Burrows ACRS M. Satorius, Rll e-mail RCN - SE only l}}