ML19332F065
| ML19332F065 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom, Limerick, 05000000 |
| Issue date: | 11/30/1989 |
| From: | Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TASK-***, TASK-OR GL-89-21, NUDOCS 8912130344 | |
| Download: ML19332F065 (11) | |
Text
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b g,s GL-89-21
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-PHILADELPHIA ELECTRIC COMPANY NUCLEAR GROUP HEADQUARTERS j
955 65 CHESTERBROOK BLVD.
WAYNE, PA 19087 5691 j
J tris) sso sooo November 30, 1989-a Docket Nos. 50-277 50-278' 50-352 50-353-License Nos. DPR-44 L
.U.S.
Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Peach Bottom Atomic Power Station, Units 2 and 3 Limerick-Generating Station, Units 1-and 2 Response to Generic Letter 89-21, " Request For Information Concerning Status Of Implementation Of Unresolved Safety.
Issue (USI)-Requirements" Gentlemen:
Enclosed is-Philadelphia Electric Company's response to the o
subject. Generic Letter for Limerick Generating Station (Enclosures 1 L
and;2) and Peach Bottom' Atomic Power Station (Enclosures 3-and 4).
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'This provides an update on the status of USI requirements L
implementation in accordance with the instructions of-the Generic Letter.
I If you have any questions, or require additional information, please do not hesitate to contact us.
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Very truly yours, a
A.a. A p.p.
G. A. Hunger, Jr.
8912130344 891130
'y Director-Licensing ADOCK05000}7 Nuclear Services Department DR Enclosures cc:
W. T. Russell, Administrator, Region I, USNRC gj p_
p J. J. Lyash, USNRC Senior Resident Inspector, PBAPS i
T. J. Kenny,.USNRC Senior Resident Inspector, LGS e;
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Docket Nos. 50-352 50-353-LIMERICK GENERATING STATION
. ENCLOSURE 1 UNITS 162n
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UNRESOLVED SAFETY ISSUES FOR WilICil A FINAL TECHNICAL RESOLUTION HAS BEEN ' ACHIEVED USI/MPA m
NUMBER
' TITLE
'REF. DOCUMENT
' APPLICABILITY
' STATUS /DATE*'
REMARKS A-1 Water llamer SECY:84-119-All NC
.NUREG-0927, Rev. I NUREG-0993, Rev. 1 NilREG-0737 Item I.A.P.3 SRP-revisions' A-2/
Asymmetric Blowdown NUREG-0609
-PWR NA Not a PWR' MPA D-10 Loads on Reactor Primary GL 84-04, GDC-4 Coolant Systems A-3 Westinghouse Steam NUREG-0844 W-PWR NA.
Not a'PWR' Generator Tube Int'egrfty SECY 86-97 SECY 88-?72 GL 85 l (No requirements) 4 A-4 CE Steam Generator Tube NUREG-0844, SECY 86-97 CE-PWR Integrity SECY 88-272 NA Not a PWR-GL:85-02 (No requirements)
A-5 88W Steam Generator NUREG-0844, SECY 86-97 R&W-PWR Tube Integrity SECY 88-272 NA Not.a PWR GL'85-02 (No Requirements)
E
'A-6 Mark I Containment NUREG-04nn Park I-BWR NA Not a Mark I Short-Term Program
- C - COMPLETE.
. ** See Enclosure'2:
NC - NO CilANGES NECESSARY-NA - NOT APPLICARLE I - INCOMPLETE E - EVALUATING ACTIONS REQtilRED a
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'LCS U2ite l&2'
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USI/MPA NUMBER.
TITLE REF. DOCllP'FNT APPLICAR TLITY STATUS /DATE*..
REMARKS A-7/
Mark I long-Term NUREG-0661.
Mark I-RWR.
NA Not a Mark I I)-01 Program NUREG-0661 Suppl. 1 GL 79-57 A-8 Mark II Containment NUREG-0808 Mari 11-863 NC Pool Dynamic Loads NUREG-0487, Suppl. 1/2 NUREG-0802 SPP 6.2.1.1C
-GDC 16 A-9 Anticipated Transients NUREG-0460, Vol. 4 All Unit 1: c 6/89 Without Scram 10 CFR 50.f,2 Urft 2: NC A-10/
BWR Feedwater Nozzle NUREG-0619 RWp NC MPA B-25 Cracking Letter from DG Eisenhut dated 11/13/80 GL 81-11 A-Il Reactor Vessel Material NOREG-0744, Rev. I All NC Toughness 10 CTR 50.60/
8?-26 A-12 Fracture Toughness of NUREG-0577 Rev. 1 PWP NA Not a PWR Steam Generator and SRP Revision Reactor Coolant Pump 5.3.4 Supports A-17 Systems Interactions Ltr:
DeYoung to All NC Ifcensees - 9/77 NUREG-il74 NUREG-1229, NUREG/CR-3922 NUREG/CR-4261, NUPEG/
CR-4470, GL 89-18 (No requirements)
A-24/
Qualification of Class MUREG-0588, Icev. I All Unit 1: c 3/85 MPA B-60 IE Safety-Related SRP 3.11 Unit 2: NC Equipment 10 CFR 50.49 GL 82-09. Gl. 84-24 GL 85-15
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LGS Units 1&2 USI/MPA NtMBER TITLE REF. DOCUMENT APPLICABILITY STATUS /DATE*
REMhRKS A-26/
Reactor Vessel Pressure DDR Letters to PWR NA.
Not a PWR MPA 0-04 Transient Protection Licensees 8/76 NUREG-0224 NtfREG-0371 SRP 5.2 GL 88-11 A-31 Residual Heat Removal WilREG-0606 All Ols After NC Shutdown Requirements RG 1.113, 01/79.
Control of Ifeavy Loads NUREG-0612 All Unit 1: C 5/85 C-10, Near Spent Fuel SNP 9.1.5 Unit 2: NC C-15 GL 81-07, GL 83-42, GL 85-11 Letter from DG Eisenhut dated 12/22/80 A-39 Determination of SRV NilREG-0802 RWR NC Pool Dynamic loads NUREGs-0763,0783,0802 and Pressure Transients NUREG-0661 SPP 6.2.1.1.C d
A-40 Seismic Design SRP Revisions NUREG/
All NC Criteria CR-4776 NUREG/CR-C054, NUREG/CR-3480, NUREG/
CR-1582, NUREG/CR-1161, NURFG-1233, NOREG-4776 NtIREG/CR-3805 NUREG/CR-5347 NUREG/CR-3509 A-42/
Pfpe Cracks in Ilofling NilREG-0313. Rev. 1 BWR Unit 1: C 5/89 MPA 11-05 Water Reactnrs NilRfG-0313. Rev. 2 Unit 2: I GL 81-03, GL 88-01 Proj ected: 7/91 2
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t.Gs Unita'It.2 1, '
USI/MPA-4 -
. NUMBER TITLE REF. DOCIMENT APPLICABILITY STATUS /DATE*
REMARKS A-43 Containment' Emergency NilREG-0510 All NC Sump Perfomance NUREG-0869, Rev. 1 NUREG-0897, R.G.I.87 (Rev. 0), SRP 6.2.2 GL 85-22 No Requirements A-44 Station Blackout RG I.155 All I
NUREG-1032 Projected: 4/91 NUREG-1109 10 CFR 50.63 A-45 Shutdown Decay Heat SECY 88-260 All I
Removal Requirements NUREG-1289 Projected: 7/92 Covered by IPE NUREG/CR-5230 SECY 88-260 (No requirements)
A-46 Seismic Qua11fication NUREG-1030 All NA of Equipment in NUREG-1211/
Operating Plants GL 87-02, Gt 87-03 A-47 Safety Implication NUREG-1217, NUREG-All E
CL 89-19 Response, of Control Systems I?]n due 3/90 GL 89-19 A-40 flydrogen Control 10 CFR 50.44 All, except Unit 1: c Measures and Effects SECY 89-1??
PWRs with Unit 2: I of flydrogen Burns on Safety Equfpment.
Idrge dry Projected: 2/90 containments A-49 Pressurized Thermal PGs 1.154, 1.99 PWR NA
'Not a PWR Shock SECY 82-465 SECY E3-288 SECY 81-687 10 CFR 50.61/
GL H8-11
5 Dockot Nos. 50-352 Enclonuro 2 50-353 I
LGS REMARKS 1
A-9:
See Unit 1 License Amendment No. 22.
A-17:
IPE is expected to address internal flooding scenarios.
A-24:
See Unit 1 License Condition No. 5.
I A-36:
See Unit 1 License Condition No. 19.
A-42:
See Generic Letter 88-01 Response dated 8/2/88.
LGS Unit 2 In-Service Inspection (ISI) program revision is scheduled to be completed during the next refueling outage.
A-44:
See Rule Response dated 4/17/89.
No modifications are needed.
Procedure revisions will be complete within one year of NRC notification.
A-46:
See FSAR and NRC SER Section 3.10.
Originally reviewed to IEEE 344-1975 requirements.
A-48:
See FSAR and NRC SER Section 6.2.5.
See Unit 2 Exemption from 10 CPR 50.44 in License Condition 2.D(e).
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.P f;
t Dockst Noa. 50-277 50-278 PEACII BOTTOM ATOMIC POWER STATION ENCLOSURE 3 G
Units 2&3 UNRESOLVED SAFETY ISSUES FOR WIIICH A FINAL TECHfilCAL RESOLUTION HAS BEEN ACHIEVED
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USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS /DATE*
REMARKS
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A-1 Water llammer SECY 84-119 All NC NUREG-09?7, Rev. 1 NtIREG-0993, Rev. I NilREG-0737 item I.A.7.3 SRP revisions A-2/
Asymmetric 810wdown NUREG-0609 PWR NA Not a N MPA D-10 Loads on Reactor Primary GL 84-04, GDC-4 Coolant Systems i
A-3 Westinghouse Steam NUREG-0844 W-PWR NA Not'a PWR renerator Tube Integrity SECY 86-97 SECY 88-?72 GL 85 (No requirements)
A-4 CE Steam Generator Tube NUREG-0844, SECY 86-97 CE-PWp NA Not a PWR Integrity SECY 88-272 GL 85-02 (No requirements)
A-S 88W Steam Generator.
NilREC-0844. SECY 86-97 88W-PWp NA Not a PWR Tube Integrity SFCY 88-272 GL 85-02 (No Requirements)
E l-6 Mark I Containment NOREG-0408 Fark l-BWR c 12/76 Short-Term Program
- C - COMPLETE
- See Enclosure 4 NC - NO CllANGES NECESSARY NA - NOT APPLICARLE I - INCOMPLETE E - FVALUATING ACTIONS REQilIRED
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PBAPS Unito 2&3
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-p-USI/MPA NUMBER TITLE
.REF. DOCUMENT APPLICABILITY STATUS /DATE*
REMARKS A-7/
Mark I long-Term NUREG-0661 Mark i-BWR c
D-01 Program NUREG-0661 Suppl. I Unit 2: 4/89 GL 79-57 Unit 3: 6/87
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A-8 Mark Il Containment NUREG-0808 Mark II-BWR NA Not a Mark 11 Pool Dynamic Loads NUREG-0487, Suppl. 1/2 NUREG-0802 SPP 6.2.1.IC
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GDC 16 A-9 Anticipated Transients NUREG-0460, Vol. 4 All c (mods installed)
Without Scram 10 CFR 50.62 Unit 2: 3/89 Unit 3: 9/89 A-10/
BWR Feedwater Nozzle NOREG-0619 PWR c 8/81 NPA B-25 Cracking Letter from DG Eisenhut dated 11/13/80 GL 81-11 A-11 Reactor Vessel Material NUREG-0744, Rev. I All NA Toughness 10 CFR 50.60/
82-26 A-12 Tracture Toughness ~ of NUREG-0577, Rev. I PWP NA Not a PWR Steam Generator and SRP Revision Reactor Cooiant Pump 5.3.4 Supports 4
A-17 Systems Interactions Ltr:
DeYoung to A11 c 1/81 Ifcensees - 9/77 MUREG-1174. NUREG-1229, NUREG/CR-3922.
NUREG/CR-4761, NtrPEG/
CR-4470, GL 89-18.
(No requirements)
A-24/
Qualification of Class NOREG-0588, I:ev.-:
All c
MPA B-60 IE Safety-Related SRP 3.11 Unit 2: 12/85 Equipment 10 CFR 50.49 Unit 3: 11/85 y
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.l ! j PBAPS Unito 2&3
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USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS /DATE*-
REMARKS A-26/
Reactor Vessel Pressure DOR Letters to PWR NA Not a PWR MPA B-04 Transient Protection Licensees 8/76 NUREG-0224 NUREG-0371 SRP 5.2 GL 88-11 A-31 Residual Heat Removal NUREC-0606 All Ols After NA OL prior to 01/79 Shutdown Requirements RG 1.113 01/79.
A-36/
Control of Ileavy Loads NUREG-0612 All c 2/86 C-10, Near Spent Fuel SRP 9.1.5 C-15 GL 81-07, GL 83-42, GL 85-11 Letter from DG Eisenhut dated 12/22/80 A-39 Determination of SRV NUREG-0802 BWR NA Pool Dynamic loads NUREGs-0763,0783,0602 and Pressure Transients NUREG-0661 SPP 6.2.1.1.C d
A-40 Seismic Design SRP Revisions, NUREG/
All NA Criteria CR-4776, NUREG/CR-0054, NilHEG/CR-3480, NOREG/
CR-1582, NUREG/CR-1161 NURfG-1233 NUREG-4776 NUREG/CR-3805 NOREG/CR-5347 NUREG/CR-3509 A-42/
Pipe Cracks in Bolling NUREG-0313, Rev. 1 BWR I
MPA B-05 Water Reactors NURfG-0313 Rev. 2 Projected:
GL 81-03, GL 88-01 Unit 2: 4/91 Unit 3: 12/91
PZAPS Units 2&3 d' USI/MPA 4
NUMBER' TITLE REF. DOCUMENT APPLICABILITY STATUS /DATE*
REMARKS A-43 Containment Emergency NUREG-0510, All NC Sump Performance NUREG-0869, Rev. 1 NilREG-0897, R.G.I.87 (Rev. 0), SRP 6.2.2 GL 85-22 No Requirements A-44 Station Blackout RG 1.155 All I
NUREG-1032 Projected: 4/91 NUREG-1109 10 CFR 50.63 A-45 Shutdown Decay lleat SECY 88-26G All I
Removal Requirements NOREG-1289 Projteted: 9/92 Covered by IPE NUREG/CR-5230 SECY 88-260 (No requirements)
A-46 Seismic Qualification NUREG-1030 All I
of Equipment in NUREG-1211/
Projected:
Operating Plants GL 87-02, Gl. 87-03 Unit 2: 4/91 Unit 3: 11/91 A-47 Safety Implication NUREG-1217, NifREG-All E
GL 89-19 Response of Control Systems 1218 4
due 3/90 GL 89-19 A-48 flydrogen Control 10 CFR 50.44 All, except NC Measures and Effects SECY 89-172 PWRs with of Hydrogen Burns large dry on Safety Equipment conta innents A-49 Pressurized Thermal PGs 1.154, 1.99 PWR NA Not a PWR Shock SECY 82-465 SECY 83-288 SECY 81-687 10 CFR 50.61/
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- - DockCt No3. 50-277 Enclo;uro 4 50-278 l
i-t PBAPS REMARKS A-1:
The majority of features recommended in Section 2.5.1 of NUREG-0927 are employed at Peach Bottom.
A-6:
See UPSAR, Appendix M, paragraph M.3.5.
A-7:
See 3/18/87 letter, PEco to NRC, regarding modifications completion schedule.
A-9 See 4/21/89 letter, PECo to NRC, regarding ARI function time.
i A-11:
Charpy Upper Shelf Energy > 50 ft-lbs.
A-17:
See Response (received by NRC 9/1/72) to 8/4/72 NRC letter regarding internal flooding.
IPE is also expected to address internal flooding scenarios.
NUREG-0737 Item 1.C.5 has been implemented since January 1981.
A-36:
See 2/11/86 Response to Generic Letter 85-11.
A-39:
Mark I Containments are covered by USI A-7.
A-40:
Construction Permit prior to 1972, thus, covered by USI A-46 (vertical tanks).
A-42:
See Generic Letter 88-01 Response dated 8/2/88.
Pipe replacements at PBAPS, Units 2 and 3, are tentatively scheduled to be completed during the next refueling outage for each unit.
A-43:
See 5/29/87 letter, PECo to NRC, regarding piping replacement modifications.
Modifications performed since issuance of Revision 1 to Reg. Guide 1.82 have conformed to Revision 1.
Company has initiated programmatic changes to ensure future conformance to Revision 1 to Reg. Guide 1.82.
i' A-44:
See Rule Response dated 4/17/89.
No modifications are needed.
Procedure revisions will be complete within one year of NRC notification.
A-46:
Projected implementation dates provided are the scheduled dates of plant walk-downs per the SQUG GIP once the GIP is approved by the NRC.
A-48:
See 6/26/85 NRC SER.
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