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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARNOC-AE-000661, Rev 4 to Severe Weather Plan, Including Summary of Changes.With1999-10-0404 October 1999 Rev 4 to Severe Weather Plan, Including Summary of Changes.With ML20217A2421999-09-30030 September 1999 Proposed Tech Specs Removing Parameters No Longer Applicable & Adding Tdf Value for Model 94 SGs in Place of Reactor Coolant Sys Flow ML20211Q8071999-09-0808 September 1999 Proposed Tech Specs & Associated Bases for Specification 3/4.8.1, AC Sources, to Eliminate Requirement for Accelerated Testing of Standby DGs & Associated NRC Reporting Requirements ML20211Q2361999-09-0808 September 1999 Proposed Tech Specs 3/4.8.1,revised by Relocating 18-month Surveillance to Subject Sdg to Insps IAW Procedures Prepared in Conjunction with Mfg Recommendations to Section 3.8.1.1.4.8 of UFSAR ML20211G2281999-08-24024 August 1999 Proposed Tech Specs Pages,Relocating Cycle Specific Operating Parameters from TSs to Colr,Including Moving Location of Insert 6 from Page 6-21 to Page 6-22 of Administrative Control Section & Renumbering Methods List ML20211C0371999-08-18018 August 1999 Proposed Tech Specs 3.4.9.3 Re Cold Overpressure Mitigation Curve Associated with Replacement SGs ML20210J0481999-07-28028 July 1999 STP Unit 1,Cycle 9 Startup Testing Summary Rept ML20209G9351999-07-15015 July 1999 Proposed Tech Specs 3.7.1.6 Re Atmospheric Steam Relief Valves ML20209H2131999-07-13013 July 1999 Rev 4,revised Pages 29 & 30 of 102 to Procedure 0ERP01-ZV-IN01, Emergency Classification ML20209H3371999-07-13013 July 1999 Rev 0 to 0PGP02-ZA-0004, Station Performance Data Collection,Categorization & Reporting ML20209G4461999-07-13013 July 1999 Proposed Tech Specs,Modifying 3.6.3 Action B,Clarifyin Use of Check Valve with Flow Through Valve Secured as Means to Isolated Affected Containment Penetrations ML20209C1511999-07-0101 July 1999 Proposed Tech Specs Pages Re Amend to License NPF-80, Changing TSs 3.3.2 & 3.7.8 Allowing All Fuel Handling Bldg Exhaust Air Sys Components to Be Inoperable for Period of 8 Hours to Facilitate Repair of Train B Exhaust Booster Fan ML20209B5341999-06-24024 June 1999 Proposed Tech Specs Section 6.9.1.6.a,adding Min Measured RCS Flow,Which Lists Parameters Included in COLR ML20209H3151999-06-23023 June 1999 Rev 4 to 0PGP02-ZA-0003, Comprehensive Risk Management ML20195E4211999-06-0707 June 1999 Proposed Tech Specs,Relocating cycle-specific RCS-related TS Parameter Limits to COLR ML20195E4701999-06-0707 June 1999 Proposed Tech Specs Pages Re Proposed Amend to Licenses NPF-76 & NPF-80,deleting Total Allowance,Sensor Error & Z Terms from ESFAS & RTS Instrumentation Trip Setpoint Tables of TS 2.2.1 & 3.3.2 ML20209H3081999-06-0101 June 1999 Rev 3 to 0PGP04-ZA-0604, Probabilistic Risk Assessment Program ML20205S3511999-04-19019 April 1999 Proposed Tech Specs Bases Page 3/4 8-3 Removing Reference to Fast Transfer Capability That Is Inconsistent with STP Design Bases as Described in UFSAR Chapters 8.2 & 8.3 ML20205G8081999-03-30030 March 1999 Proposed Tech Specs,Relocating Section 3/4.3.3.4, Meteorological Instrumentation & Associated Bases Description to STP Trm,Per NUREG-1431 ML20204J9681999-03-22022 March 1999 Proposed Tech Specs Incorporating New TS for Atmospheric Steam Relief Valve Instrumentation & Revising TS 3.7.1.6 Re Atmospheric Steam Relief Valves ML20204D1581999-03-15015 March 1999 Proposed Tech Specs 3/4.7.9 for Snubbers to TRM ML20207D9651999-03-0202 March 1999 Proposed Tech Specs Change Clarifies Use of Check Valve with Flow Through Valve Secured as Means to Isolate Containment Penetration in TS 3.6.3 Action B ML20207C4721999-02-24024 February 1999 Proposed Tech Specs Bases 3/4.2.5,clarifying That Averaging of Only Three Channels Is Min Expected When Verifying DNB Parameter Compliance ML20202G6871999-01-26026 January 1999 Proposed Tech Spec Page 3/4 4-39,revising TS 4.4.10 for Alternate ISI of RCP Flywheels ML20199K5681999-01-20020 January 1999 Proposed Tech Specs Surveillance Requirement 4.7.1.2.1.a Re AFW Pump Performance Testing ML20198A2181998-12-10010 December 1998 Revised TS Pages,Adding Ref to TS Figure 2.1-2 to Bases Section 2.1.1 as Figure Provides DNBR Curves Appropriate to Alternate DNB Operating Criteria ML20198A1951998-12-0909 December 1998 Corrected TS Bases Pages B 3/4 8-15,-16 & -17,as Discussed During 981103 Telcon ML20196B8121998-11-23023 November 1998 Proposed Tech Specs Pages for Proposed Amends to Licenses NPF-76 & NPF-80,relocating Descriptive Design Info from TS 3/4.7.1.1 (Table 3.7-2) Re Orifice Sizes for Main Steam Line Code Safety Valves,To Bases Section ML20155J9031998-11-0303 November 1998 Proposed Corrected Tech Specs Bases 3/4 9-3 Re Water level- Refueling Cavity & Storage Pools ML20155D5441998-10-29029 October 1998 Proposed Tech Specs Pages for Proposed Amend to Relocate Turbine Overspeed Protection TS 3/4.3.4 to TRM ML20155D5561998-10-29029 October 1998 Proposed Tech Specs Pages for Proposed Amends to Relocate Snubber TS 3/4.7.9 to TRM ML20155D5801998-10-29029 October 1998 Proposed Tech Specs Pages for Amends to Relocate Portion of TS Surveillance Requirement for DG Fuel Oil Storage Tank to TRM ML20154M1621998-10-12012 October 1998 Revised Tech Specs Bases Pages B3/4 8-14 Through -17 ML20154C0051998-09-30030 September 1998 Proposed Tech Specs Reflecting Replacement SG Tube Insp Surveillance Differences & Deleting Provision Allowing Use of F* Alternate Repair Criteria ML20154C5071998-09-30030 September 1998 Proposed Tech Specs Bases Page B 3/4 9-2,removing Wording Re 10% Value for Clad Gap Iodine Isotopics ML20154A4281998-09-28028 September 1998 Proposed Tech Specs Re Requirements Associated with Control Room & Fuel Handling Bldg Ventilation Sys ML20151T1621998-08-31031 August 1998 Proposed Tech Specs 3.4.9.3 Re Cold Overpressure Mitigation Curve Associated W/Replacement SGs ML20238F0841998-08-28028 August 1998 Proposed Tech Specs Section 4.0.5,excluding Specified Containment Isolation Valves from ISI & Testing Requirements as Stated in Section XI of ASME Boiler & Pressure Vessel Code ML20236T5141998-07-22022 July 1998 Proposed Tech Specs Re Replacement SG Water Level Setpoint Differences ML20236R1461998-07-15015 July 1998 Proposed Changes to Current Tech Specs Bases ML20236L6311998-07-0707 July 1998 Proposed Tech Specs,Reflecting Rev of Criticality Analyses & Rack Utilization Schemes for Regions 1 & 2 of Spent Fuel Racks as Described in STP UFSAR & TSs ML20236K3481998-07-0606 July 1998 Proposed Tech Specs,Relocating 3/4.7.13 Requirements for Area Temp Monitoring Sys to Technical Requirements Manual ML20236M6381998-07-0606 July 1998 Proposed Tech Specs,Relocating 3/4.3.3.3 Requirements for Seismic Instrumentation to Technical Requirements Manual ML20236N0001998-07-0606 July 1998 Proposed Tech Specs,Relocating RCS Design Features from TS Section 5.4 to UFSAR ML20247F3321998-05-0707 May 1998 Proposed Tech Specs Pages,Reflecting Replacement SG Reactor Coolant Flow Differences ML20217P1441998-04-0202 April 1998 Proposed Tech Specs 3.4.5 Re voltage-based Repair Criteria ML20202H9771998-02-16016 February 1998 Proposed Tech Specs Pages,Implementing 1-volt voltage-based Repair Criteria for SG Tube Support plate-to-tube Intersections ML20198C3741997-12-31031 December 1997 Proposed Tech Specs 2.1,2.2 & 3/4.2.5 for Alternate Operation W/Reduced Measured RCS Flow ML20197A7211997-12-17017 December 1997 Proposed Tech Specs Pages,Revising TS 4.6.2.1 to Extend Surveillance Interval of Containment Spray Sys Nozzle Air Flow Test from Five Years to Ten Years ML20199H2081997-11-20020 November 1997 Revised TS Bases Page B 3/4 4-15 1999-09-08
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARNOC-AE-000661, Rev 4 to Severe Weather Plan, Including Summary of Changes.With1999-10-0404 October 1999 Rev 4 to Severe Weather Plan, Including Summary of Changes.With ML20209H3371999-07-13013 July 1999 Rev 0 to 0PGP02-ZA-0004, Station Performance Data Collection,Categorization & Reporting ML20209H2131999-07-13013 July 1999 Rev 4,revised Pages 29 & 30 of 102 to Procedure 0ERP01-ZV-IN01, Emergency Classification ML20209H3151999-06-23023 June 1999 Rev 4 to 0PGP02-ZA-0003, Comprehensive Risk Management ML20209H3081999-06-0101 June 1999 Rev 3 to 0PGP04-ZA-0604, Probabilistic Risk Assessment Program ML20212G0031997-10-21021 October 1997 Rev 2 to OPGP-04-ZA-0002, Condition Rept Engineering Evaluation Program ML20209H3321997-07-31031 July 1997 Rev 2 to 0PGP01-ZA-0304, Probabilistic Safety Assessment Risk Ranking ML20198E8411997-05-22022 May 1997 Rev 4 to 0PGP05-ZA-0002, 10CFR50.59 Evaluations ML20217G8191997-02-15015 February 1997 Rev 16 to 0POP03-ZG-0009, Mid Loop Operation ML20198E8511996-10-28028 October 1996 Rev 5 to 0PGP05-ZA-0002, 10CFR50.59 Evaluations ML20134J9951996-09-11011 September 1996 South Tx 1 Fuel Assembly Insp Program ML20148C9531996-07-15015 July 1996 Rev 0 to 0PGP04-ZA-0604, Probabilistic Safety Assessment Program ML20217F0001996-04-0101 April 1996 Rev 0 to Usqe 96-0101, Control Room Envelope HVAC Emergency Makeup Flow Control Damper B2HEFCV9585 Temporary Mod ML20097D4021996-02-0202 February 1996 Rev 0 to 0PGP02-ZA-0004, Station Performance Data Collection,Categorization & Reporting ML20097D3751996-02-0202 February 1996 Rev 0 to 0PGP02-ZA-003, Comprehensive Risk Mgt ML20097D3821996-01-0202 January 1996 Rev 0 to 0PGP02-ZA-XXXX, Probabilistic Safety Assessment Program ML20097D3881995-10-30030 October 1995 Rev 0 to 0AAA00-AA-0000, Configuration Control of Probabilistic Safety Assessment ML20149E0061995-10-20020 October 1995 Rev 1 to Procedure Usqe 92-0022, Proposed Change Evaluates Doses from Leakage of Sump Water Into Rwst ML20149E0561995-10-20020 October 1995 Rev 2 to OPGP05-ZA-0002, 10CFR50.59 Evaluations, Form 2 ML20093E7361995-10-0202 October 1995 Rev 0,Suppl 1 to ISI Plan for First Insp Interval of South Tx Project Electric Generating Station Unit 1 ML20149E0321995-06-0404 June 1995 Rev 2 to Procedure OPGP05-ZA-0002, 10CFR50.59 Evaluations, Form 1 ML20080G9091994-12-31031 December 1994 1999 Business Plan ML20217G8141994-11-22022 November 1994 Rev 2 to 0PGP03-ZA-0101, Shutdown Risk Assessment ML20078Q2561994-11-0707 November 1994 Rev 6 to OPMP04-JC-0002, Polar Crane Insp ML20078C5971994-10-26026 October 1994 Rev 4,Suppl 2 to STP Electric Generating Station Unit 2 Pump & Valve IST Plan ML20078C5961994-10-26026 October 1994 Rev 6,Suppl 2 to STP Electric Generating Station Unit 1 Pump & Valve IST Plan ML20078Q5651994-10-17017 October 1994 Rev 6 to OPGP03-ZX-0002, Condition Reporting Process ML20078Q7291994-10-17017 October 1994 Rev 10 to OPGP03-ZA-0090, Work Process Program ML20078Q8051994-10-17017 October 1994 Rev 2 to OPGP04-ZE-0310, Plant Mods ML20078Q5081994-08-29029 August 1994 Rev 7 to OPMP02-ZG-0011, Alternative Valve Packing & Live- Load Valve Packing ML20078Q5581994-06-24024 June 1994 Rev 5 to OPGP03-ZX-0002, Corrective Action Program ML20078Q7801994-06-0101 June 1994 Rev 2 to OPEP07-ZE-0007, MOV Tracking & Trending Program ML20078Q4021994-05-24024 May 1994 Rev 7 to OPOP01-ZA-0001, Plant Operations Dept Administrative Guidelines ML20064N4561994-03-21021 March 1994 South Tx Project Electric Generating Station Operational Readiness Plan Unit 2 ML20078Q5521994-03-0808 March 1994 Rev 2 to OPOP02-AF-0001, Auxiliary Feedwater ML20078Q2581994-02-14014 February 1994 Rev 5 to OPGP03-ZM-0021, Control of Configuration Changes ML20078Q5671994-01-25025 January 1994 Rev 8 to OPGP03-ZA-0090, Work Process Program ML20063K3251993-12-23023 December 1993 300 Ton Essential Chiller Bypass Mod Verification Test ML20058C4771993-10-25025 October 1993 Rev 0 to STP Restart Action Plan ML20083P6821993-10-19019 October 1993 Rev 1 to Dept Procedure 0POP05-EO-EC00, Loss of All AC Power ML20078Q7851993-10-15015 October 1993 Rev 0 to, Equipment History Program ML20058N7821993-10-14014 October 1993 STP 1994-98 Business Plan ML20083P6831993-09-15015 September 1993 Rev 2 to Dept Procedure 0POP04-AE-0001, Loss of Any 13.8 Kv or 4.16 Kv Bus ML20046A2161993-07-15015 July 1993 Field Change 93-1163 to Rev 0 to Procedure 0PGP05-ZV-0008, Siren Sys Activation,Testing & Documentation, Adding Caution to Conducting Manual Growl Test ML20062L1461993-07-0606 July 1993 Rev 3 to Speakout Program Instruction SPI-02, Classification of Concerns ML20045E9781993-06-29029 June 1993 Rev 4 to Pump & Valve IST Plan, for Stp,Unit 2 ML20045E9901993-06-29029 June 1993 Rev 6 to Pump & Valve IST Plan, for Stp,Unit 1 ML20078Q2751993-06-28028 June 1993 Rev 5 to ISEG-01, Independent Safety Engineering Group Organization & Responsibilities ML20062L2301993-03-0202 March 1993 Rev 2 to Speakout Program Instruction SPI-08, Speakout Review Committee ML20062L2101993-03-0202 March 1993 Rev 2 to Speakout Program Instruction SPI-07, Speakout Repts 1999-07-13
[Table view] |
Text
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OFGP05-ZA-0002 Itcv,.1 14e 38 of 44 10CFRSO.59 Evaluations Fonni 10CFR$0.59 Screening Form (Sample) 14e I or i UNIT #1 "
O orSA" " O 'S*" C'*'
O "i'"
O uNrrr2 g oom ORIGifMUNG DOCUMENT NO. Suppdement to USQE 9G4046 REV.NO. 0 DESCRIPTION OF CIW4GE Make editorial manges to USQE 9G0040, added reviewers clarifcaton notes ( secton A1.ll eM the summt.ty) i PREUMitWlY SCRED41NG YES NO
- 1. Does the proposed change represent a change to the Plant Technical Spedfcatons?
g
- 2. Is an Unreviewed Safety Queston known to te assodated with the sut(ed change?
O O NOTE: if 'YES* to eitter questons 1 or 2 refer to OPGP0b7N4004.
I Does the proposed dange represent
- 3. A dange to only corred a typographk:& , editorial or drafung error?
g
- 4. A change wtuch is Wentcal to and addressed in its entirety t>y an existing approved 10CFR50.69 SaeonirgUSQE or NRC approved hcensing autmittat?
Wl 0
- 6. A spare or replacement part/ component change with an equkalent part/ component?
(See Secton 2.3 for a definNon of equNalent) O x
- 6. A configuraton change within exisung design spedfcatons?
x if all answers to the above questons are *NO" perform the final screening and mark ifA in th6 amroval bloc 6.s telow.
If the answer to any question (3) through (6)is 9ES* a final screening is not necessary.
Sion approval t4ocks below and discard pages 2 and 3.
Prov6de a justficaton and references if any of tems (3) through (6) is answered 'YES*.
This change danfes statemt:nts made in the orignal USOE, these changes are edaonal and does not change the basis of the onginal USQE and ts bounded by the ortginal 60 69 cvaluaton.
/ Onynator Date
_h A hh n Qualifed Revewer g
Date g
9708110029 970804 PDR ADOCK 05000498 F PDR
'g alti Plant Operations Review Consnittee --
l PORC REVIEW COVER SilEET Originating Document No. Us0E 96-0046 Revision No. -
0 TITLE _ Revise FMAR _ From Dual Train Protection To sinole Train Protection i
The PORO has reviewed this item and has determined that (check as appropriate)
It_ does_
/
does li2I involve an UHREV1BWED SAFETY QUESTION. , ;
J It does /oes d li2I adversely impact plant nuoloar saf ety,.
/does It _ does liQI adversely impact the health and safety of plant
. personnel or the public.
It does does liQI require further review by the Plant Mgr, the NSRB, or other individuals / groups. ,
M lant Hgr #NSRB other, specify below.
U1 / U3
. REMARKS 4
The PORC recommendo thio item for APPROVAL DISAPPROVAL OTHER PORC HELP 3NO NO. 96-dd?
Completed by [ DATE /0 2,) /
PORC SecWtary This form, when comp 30ted, SHALL be retained in accordance with the retention requiremonte of the originating document.
< I
4Gb Ol'Gl'05.ZA 0002 Hev. 5 l'8te of 10CFit$0.$9 thaluations Ibrm 2 Unreviewed Safety Question llY&luttlon Ibfm (S&mpf t) I' age l of 4 Untoviewod Safet/ Ooostion Evaluation # 900040 Rov. No. O Papo 1 of 0 OrlpinatinD Documont: CR 00 7092 Rev No.O NOTE: Attach 100FR50.69 Scrooning Form or Lloonso Complianoo Rovfow Form to this USOE. l 1PNS W.M6 System two lottor designator or structuro name J1!A UNIT 1 O UNIT 2 O DOTN O NTE: Uso additional t. hoots as nocessary to provido the bases. .
A.1
- 1. Doos the subjoet of this ovaluation Inoroaso the probability of -
ooourronoo of an oocident previously evaluated in tho Saloty Analysts Hoport?
O YES B 'NO Dasos: 800 attachod shoot.
- 11. Does the subjoet of this ovaluation Inoroaso tho consequenoos of an accident provlously ovaluated in tho Safety Analysis Report?
O YES S NO Dasos: Soo attachod shoot.
Ill. Does the sutJoct of this ovaluation increaso the probability of occurrence of a malfunction of equipment important to safoty previously ovaluated in the Safety Analysis Report?
O YES S NO Datos: 600 attached shoot.
IV. Does the subject of this ovaluation Inoroaso tho consequences of a malfunction of equipmont important to cafoty provlously evaluated in tho Safoty Analysis Roport?
O YES S NO Dasos: Soo attached chool.
i l
)
. I
, 'N ]
4 USQE 96 0044 REV 0. Page 2 of 5 j
A1.1(continued)
'_ The 6uta cat of this evaluelion does ret increcee the the FHA 4. The accident of conoom is a tre in any of occurrence of an econdent as evaluated in Fire which prevents theplaat from achieving 4
poet Are safe shutdown. The probabluty of a pierd le assumed tW the FHAR to be 1.0', so the '
probabluty of a tre in the pierd can not be Inoressed. Appendit R,5ecelon 111.0 requires that one trein of
, og capable of a$leving and maintelning post Are safe shutdown remain avallable, and this oment wlN continue to be met. Since the autqled of this oveidelion does not impelt the plant's abluty to
! achieve and maintain post Are safe shutdown, the probability of an accident ocouning whid win prevent the
- plant from achieving poet are oefe shuidown is not inasened.
1
- A 1.11 1
This evaluation shows no incrosse in the consequences of an sooident previously evalueled in the FHAR.
Post fire solo shutdown of the fient een be seleved for ese Fire Ares usino credited not affected by the tro. That is at least one poet tre este shutdown wilremain inaRtro i; arose. The previous esto shutdown aseeeement reached a simner ,
- There wtB be noinsosesin I
public dose due a trein any Fire Area.
- l 'An updele to the STP PSA was performed on selected tre zones to determine the ofremoving Thermo4.ag on the postulated Fire induced Core Damage F (COF)and tie induced I.arge Early Release F (LERF). The update concluded that failures of Thermo4a i
! (will) have a impact on the risk of core demeGe and large earty release at STPOE8,p Therefore, barrier 6 j the consequences of a fire in any area are riot increased. ,
A.1.Ill(continued) d above, the sub ityof 1
As explained an mooident in item (1)d in the as evaluate andFHAR, thereforejectit does of notthisincrease evaluation the does ofnot incrosse the
- - equipment malfunction. 'ihe equipment of conoom in this evaluation is that equipment comprising i the available to fire safe shutdown. Since one path remains available and free of l - fire damage, of fire induced equipment malfunction adversely affecting post Are j safe shutdown is notincrossed.
i .
L A1.IV(continued) 1 As explained in iteto (2) above, the subject of this evaluation does not increase the consequenoes i _of equipment malfunction. Post fire safe shutdown can be achieved for su fire areas. No -
- malfunction of the credited post fire safe shutdown pathway is postulated, f.ince it wlN remaTn free '
of fire damage. The potential adverse effects of fire induced malfunctions in the unprotected pathways have been considered in the safe shutdown analysis, and compensatory actions are taken when neces.sary. The plant's ability to achieve and maintain post fire safe shutdown is not adversely affected.
~
' Reviewers clarification noteI The original ProbabHistic Safety Analysis (PSA) did not model Thermo-lag protection. In 1994 A Fire Analysis Update (PSA for Selected Fire Zones) performed a sensitivity studiy to determine the maximum possible benefit that may be schieved by taking credit for existing Thermo-lag protection of raceways. The k
results of this analysis was that the use of Thomolag would have a negligible (decrease) impact on the risk of core dama e and la early release at South Texas Project. Therefore, the removal of, or damage l to the Thermo-la banier is unded by the original PSA results and the consequences of a fire in any area are notincreas .
/ .
i OPGP05 ZA.0002 lley. 5 h te of 10Cm$0.$9 baluations Form 2 Unreviewed Safety Question Hvaluation Form (Sample) hte 2 of 4 Untovlowod Gafoty Que5Uon EvalunUon er DO M O Rov,IJo. O Page 3 of 6 Originating Dooumont: Cfl007692 Rov.I10. 0 70
- 1. Doos the cuyoct of tho evaluaUon oroato the possit4lity of an aooldont of a difforont typo than any prodously ovalualod 10 the Safoly Analyt,ls Roport?
Dasos:
O YE0 O f10 Tho nrovious safe chutdown assessmont assumed all equipmont i.i a glvon tiro a:oa was lost as a tosult of tho ' maximum postulated firo", and demonstrated that post flro cafo t.hu Jown of the plant could be achtovod UUlldng oculpment unaffootod by the flro. Fost firo cafo shutdowri ts still assured for at eroas of the plant utilting og ont unafIotAod by the fire. Thorefore, the subjoot ol this ovaluauon does not croato the pos f an acoldont of a diffotont fype than any previously evalustod in the Safoty Anatysis Report Firo Hazards Analysis Report. ,
l
- 11. Does the suyoct of this ovaluaUon eroato the possibility of a d.fforent type of malfunction than any previously evaluated in the Saroty Analysis Report?
O YES B (JO Dasos: As explainod in A.2.1 chovo, the previous analysis assumod all equipmont in a glvon firo area was lost as a tosutt of the nnximum postulated firo. The analysts also locludod a review of all potential spurtous actuatiores whidi could advorsolv afloot post fire cafo shutdown. The sutdoet of tnis ovaluation considors thoso camo malfunctions, and thoroforo doos not oroato the possibility of a mal!Jaction not previously evaluatod.
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A.3 I. Does tho subject of this ovaluation 10d000 the margin of safoty as dofinod in the basts for any Technical Specification?
Datas:
O YES Q f40 Firo protoction and post fire cafo r.hutdown are not spocificotty addressed in tho Technical Spootfications. Thoroforo, this ovaluation doos not roduce the mar 01n of t afoty as definod in the basis for any Technical SpoolfL.ation.
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