ML18116A075
| ML18116A075 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 05/06/1993 |
| From: | Le N Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9305100208 | |
| Download: ML18116A075 (35) | |
Text
Docket No. 50-400 May 6, 1993 LICENSEE:
Carolina Power 8 Light Company FACILITY:
Shearon Harris Nuclear Power Plant, Unit 1
SUBJECT:
SUMMARY
OF MEETING HELD ON APRIL 22,
- 1993, WITH CAROLINA POWER 5 LIGHT COMPANY A meeting was held with Carolina Power
& Light Company (CP8L) on April 22, 1993, in Rockville, Maryland.
The purpose of the meeting was to discuss future submittals planned by CP8L, the status of the NRC's review of previous submittals, responses to generic communications, NRC concerns, and other general coordination of licensing activities.
The meeting participants are listed in Enclosure 1 and Enclosure 2 is the hand-out material that was used during the meeting.
At this meeting, the licensee also provided an update of their plan for the upcoming Shearon Harris Cycle 6 refueling activities.
During this presentation, the staff noted a discrepancy in one of the proposed Technical Specification (TS) change requests that the licensee had planned to submit by June 15, 1993.
A reference to a non-existing TS 4. 1. l.1.l.e was found in the Surveillance Requirement for TS 4. 1. 1. 1.2.
The staff reviewed other earlier TS changes, and found that TS 4. 1.1. l.I.e had been modified to become TS
- 4. 1. 1. 1. l.d in an earlier amendment, however the reference in TS 4. 1. 1. 1.2 was not updated at the time.
The licensee stated that they plan to submit a
separate amendment
- request, in a timely manner, to correct the error.
Sincerely, ORIGINAL SIGNED BY:
Ngoc B. Le, Project Manager Project Directorate II-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulations
Enclosures:
- 1. List of Attendees
- 2. Hand-out material cc:
See next page OFC NAME DATE LA: 'E PDA 05 93 PM: PD21: DRPE NBLe:tmw 05 93 AMi hei 05 93 Document Name:
HAR0422.MTS 9305i00208
- 930506, PDR ADOCK 05000400 P
I 2
JJ
'(
P
Mr. G.
E.
Vaughn Carolina Power 5 Light Company Shearon Harris Nuclear Power Plant, Unit 1
CC:
Mr. H.
Ray Starling Manager - Legal Department Carolina Power
- 5. Light Company Post Office Box 1551
- Raleigh, North Carolina '7602 Resident Inspector/Harris NPS c/o U. S. Nuclear Regulatory Commission Route 1,
Box 315B New Hill, North Carolina 27562 Mr. Gerald E. Vaughn, Vice President Harris Nuclear Project/Project Post Office Box 165 New Hill, North Carolina 27562 Mr. H. A. Cole Special Deputy Attorney General State of North Carolina Post Office Box 629
- Raleigh, North Carolina 27602 Public Service Commission State of South Carolina Post Office Drawer 11649
- Columbia, South Carolina 29211 Mr. G.
E.
Vaughn Vice President Shearon Harris Nuclear Power Plant P. 0.
Box 165 Mail Code:
Zone 1
New Hill, NC 27562-0165 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta St.,
N.W., Ste.
2900 Atlanta, Georgia 30323 Mr. C. S. Hinnant Plant General Manager Harris Nuclear Plant Post Office Box 165 New Hill, North Carolina 27562 Mr. Dayne H. Brown, Director Division of Radiation Protection N. C. Department of Environmental, Commerce 5 Natural Resources Post Office Box 27687 Ral eigh, North Carol ina 27611-7687 Mr. R.
B. Starkey Vice President Nuclear Services Department Carolina Power
& Light Company Post Office Box 1551
- Raleigh, North Carolina 27602
DISTRIBUTION:
cc w enclosures 1 and 2:
VDocket Fi.led NRC/Local PDRs PD II-1 Reading File N. B.
Le E.
W. Merschoff, R-II T. Murley/F. Miraglia 12-G-18 J. Partlow 12-G-18 S. A. Varga G.
C. Lainas J.
A. Mitchell P.
D. Anderson T. A. Reed T.
R. Farnholtz E. L. Jordan MNBB 3701 L. E. Phillips 8-E-23 S.
L.
Wu 8-E-23 E.
D. Kendrick 8-E-23 L. R. Plisco 17-G-21 ACRS (10)
OGC cc:
Licensee 8 Service List
NRC/CP&L Meeting April 22, 1993
~aisle Tommy Le Kenneth Karcher Bob Copeland Bob Prunty Mickey R.
Hamby Thomas R. Farnholtz Tim Reed Jocelyn Mitchell Edward Kendrick Larry Phillips Shih-Liang Wu Lewis Rowell Lewis Wells Or i ations NRC -
PD II-1 CP&L Mgr. Incore Analysis Seimens Power Corp.
CP&L Mgr.
RNP/HNP Lic.
CP&L - Mgr. Harris Reg.
Compliance NRC PD II-1 NRC -
PD II-1 NRC -
PD II-1 NRC/NRR/DSSA/SRXB NRC/NRR/DSSA/SRXB NRR/SRXB CP&L Project Engineer CP&L - Senior Engineer
ENCLOSURE 2
ATI'ACHMENT 1 18-MONTH REGULATORY AGENDA P
D Items are divided into five categories (Zl, Z2, Z3, Z4, and Z5).
Categories Zl and Z2 require some type of "NRC action" to support the plant (i.e.,
issue Technical Specification changes, approve relief requests, etc.).
Category Z3 items d~ require "NRC action" to support the plant (i.e., CP&L responses to Generic Letters and Bulletins, FSAR amendment submittal, etc.).
Category Z4 items (not attached) are those items already submitted to the NRC for which CP&L needs no response.
Closeout is tracked as an indication of additional NRC workload competing for resources with Z1 and Z2.
Category ZS items are potential Technical Specification changes or submittals which are presently unscheduled.
Items which are of greatest importance to plant operations generally are grouped in Category Z1.
Items within a category are prioritized by letter designation with "A," representing the highest priority.
Priorities are established through discussions with the Manager - Regulatory Compliance.
The "target" schedules are established through discussions with the NRC PM, recognizing plant "need dates" as well as the need to levelize demand on NRC resources.
"RD" denotes a required date to which some specific plant action is tied.
(hnp18mo)
SHNPP 18-MONTH REGULATORY SCHEDULE ATTACHMENT 2 APRIL 1993 PAGE 1
~SSUg 1993 UG SE NO DCJ 1994 P
- a*******
UG 1A/4 TRAINING TSC (TSC 92-06)
~ 3/4
~ sssassasaa
~ sasaa ~sss ~ a ~ 9/7 1B/4 DC ELECTRICAL POWER (TSC 92-02)
ISSUE TSC
~ s ~ s ~ a ~ s ~ 5/5
~ ass ~assssa
~ s ~saassssss
~ 11/5 1C/4 GAS STORAGE TANKS (TSC 92-01)
~ sasssssss 5/12
~ sasassaaasasssaassassss 11/12 1D/4 ADMIN CONTROLS PREVENT DILUTION DURING REFUELING CP&L SUBMITTAL ISSUE TSC
~ssassaass 6/15
~asaasaasasaassasssaaassssaaasasaa 3/1 RD 1D/4 AXIAL FLUX DIFFERENCE (RAOC & BASELOAD REF REPLACED BY PDC-3 AFD METHODOLOGY)
- CP&L SUBMITTAL
~ aaasasaaa 6/15 ISSUE TSC assasasssassa
~ a ~assa ~ss ~ssasaassaa 3/1 RD 1D/4 HEAT FLUX HOT CHANNEL FACTOR CP&L SUBMITTAL ISSUE TSC
~ ssssaasaa 6/15
~asaaaaasaasaaaasasssassaaaaasasss 3/1 RD Dates prior to 4/20/93 are actualsg Dates after 4/20/93 are forecasts RD ~ REQUIRED DATEg
= SCHEDULED OUTAGE I
SHNPP 18-MONTH REGULATORY SCHEDULE APRIL 1993 PAGE 2
CAT RI ISSUE 1993 R A R JUN 1994 UG SEP OCT NOV DEC JAN FEB MAR R MAY JUN JUL AUG 1D/4 CORE REACTIVITY BALANCE
~ s ~ s ~ s ~ $ $ ~ 6/15
$$ ~ a ~ asssss
~ a ~ a ~ s ~ assaassa
~ saaa
~
a ~ 3/1 RD 1D/4 SIEMENS METHODOLOGY IN COLR (REFERENCE)
~ aasssaaaa 6/15
~ sass as sass ~ $ $ ~ s ~ s ~ a ~ s sass as ass ~ s ~ 3/1 RD
]D/4 TARGET AFD (PDC III METHODOLOGY)
~sssasssaa 6/15
~ s ~ a ~ s ~ a ~ a ~ s ~ a ~ $$ ~ $$ ~ $$ ~ a ~ a ~ s ~ saa ~ 3/1 RD
]E/4 REACTOR TRIP SYST INSTRUMENTATION TRIP SETPOINTS
~ s ~ s ~ a ~ a 9/1
~saasaaaaaaaasaaasssaass 3/1 RD
~ a ~ a ~ s ~ s 9/1
~sssssssaassaaaaaaaaaaaa 3/1 RD
]E/4 F DELTA H ACTION STATEMENT
~aasaaaa 9/1
~ $ $ ~ s ~sassasa
~ s ~ a ~ a ~ $ $ ~ a 3/1 RD Dates prior to 4/20/93 are actualsg Dates after 4/20/93 are forecasts RD ~ REQUIRED DATEg
~ SCHEDULED OUTAGE
SHNPP 18-MONTH REGULA ORY SCHEDULE APRIL 1993 PAGE 3
1993 AP Y JU UG S NOV D C J 1994 R
- %***4***
UG 1E/4 STEAM GENERATOR HIGH LEVEL TURBINE TRIP
~ssassss 9/1
~ss ~ s ~ss ~ss ~ sss ~ s ~ s ~ s ~ s ~ 3/1 RD 1E/4 NEGATIVE FLUX RATE TRIP DELETION CP&L SUBMITTAL ISSUE TSC
~ sssssss 9/1
~ s ~ ssss ~ssss ~ s ~ s ~ s ~ s ~ s ~ s 3/1 RD 1E/4 RTD BYPASS TSC CP&L SUBMITTAL ISSUE TSC
~sssasss 9/1
~sssssss
~ s ~ ssssss
~ s ~ s ~ s ~ 3/1 RD 1E/4 REACTOR CORE SAFETY LIMITS CP&L SUBMITTAL ISSUE TSC
~ s ~ s ~ s ~ s 9/1
~ s ~ ssss ~ ss ~ssssss
~ s ~ s ~ s ~ 3/1 Dates prior to 4/20/93 are actualsg Dates after 4/20/93 are forecasts RD ~ REQUIRED DATEy
~ SCHEDULED OUTAGE I
SHNPP 18-MO H REGULATORY SCHEDULE APRIL 1993 PAGE 4
~C~~~R
~SS~U 1993 MA JUN UG S OCT OV C J 1994 MA UG 2A/35 LIMITING COND FOR OPERATOR ACTION REQUIREMENTS (TSC 87-12)
ISSUE TSC
~ s ~ s ~ a ~ s ~ a 5/15 2B/4 PRESSURE/TEMPERATURE LMTS REV (TSC 93-01)
ISSUE TSC
~ s ~ a ~ a ~ a ~ a ~ a ~ a ~ s ~ s ~ a ~ a ~ a 8/25 RD 2C/4 NAD FUNCTIONAL CHANGES (TSC 91-04)
ISSUE TSC
~ a ~ sa ~ sa ~ s ~ a ~ a 6/15 2D/4 RETS REMOVAL OF TABLES FROM TS CP&L SUBMITTAL (SUPPLEMENT TSC) assaaaaa 4/30 ISSUE TSC
~ saassasasasasssssssasss 10/29 2E/4 AREA TEMPERATURE MONITORING (TSC 92-03)
CP&L SUBMITTAL
~aasasass 5/7 ISSUE TSC
~ saaaaaaasssaaaaaaaaasas ll/8 2F/18 ESFAS SURVEILLANCE TESTING CP&L SUBMITTAL ISSUE TSC
~ a ~ s ~ss ~ 7/2
~aaasssssssasaaaasaasasa 12/3 2G/4 APPROVAL OF QA PROGRAM CHANGES NRC APPROVAL
~ a ~ a ~ a ~ a ~ a ~ s ~ s 6/15 Dates prior to,4/20/93 are actuals; Dates after 4/20/93 are.forecasts RD ~ REQUIRED DATEg
~ SCHEDULED OUTAGE I'
SHNPP 18-MONT REGULATORY SCHEDULE APRIL 1993 PAGE 5
~C~~~R
~SS 1993 Y JUN OCT OV C JAN 1994 UG 3A/4 GL 92-08, THERMO-LAG 330-1 (FIRE BARRIERS)
CP&L SUBMITTAL
~aaasa 4/16 3B/4 RESP TO RAI REVIEW OF ODCM
- CP&L SUBMITTAL
~ saasasa 4/28 3C/4 SUBMIT GOALS & OBJ (1993 EMERG EXERCISE)
CP&L SUBMITTAL
~ass 5/13 3D/4 ANNUAL FSAR AMENDMENT f44 CP&L SUBMITTAL bassa 6/1 3E/4 SUBMIT SCENARIO & CONT INFO (1993 EMERG EXERCISE)
CP&L SUBMITTAL
~ass 6/12 3F/4 ANNUAL ECCS EVALUATION MODEL CHANGE REPORT (10CFR 50'6)
CP&L SUBMITAL
~ass 7/26 3G/4 SEMI-ANNUAL FITNESS FOR DUTY PROGRAM DATA CP&L SUBMITTAL
~saaaasa 8/30 3H/4 GL 88-20:
SUBMIT IPE PRA FOR SEVERE ACCIDENT VULNERABILITIES (10CFR 50 54(F))
~ass 8/31 Dates prior to 4/20/93 are actualsg Dates after 4/20/93 are forecasts RD ~ REQUIRED DATEg
- +~ SCHEDULED OUTAGE
/
SHNPP 18-MONTH REGULATORY SCHEDULE APRIL 1993 PAGE 6
~SS 3I/4 RAI BULL 92-01 SUPP 1
(INFORM NRC WHEN FIRE BARRIERS ARE ACCEPTABLE)
CPQL SUBMITTAL 1993 UG SEP OCT OV D C J B
~ asssss 12/20 1994 R
Y JUN JUL AUG 3J/4 SUBMIT IPEEE ANALYSIS TO NRC CPSL SUBMITTAL (1995)
Dates prior to p/20/93 are actualsg Dates after 4/20/93 are forecasts RD ~ REQUIRED DATEp
~ SCHEDULED OUTAGE l
8/28/93 CAROLINA POMER 6 LIGHT CONPAHY S H H P P - 18 MONTH REGULATORY AGENDA - ATT '
FACTS 0 SITE PRI SONCE NCUNEHT AGEHCY UHIT HUC PRI/SCH IHD ISSUE ACTIOH QIPP-TSC-REVISED TRAIHIHG PROGRAH DESCRIPTIOH BASED OH SYSTEHATIC APPROACH TO TRAINIHG PER HRC GL 87-87 (FOR CONSISTENCY MITH FSAR CONNITNEHT)
TS e.a (TSC 92-86) 93G8829 2
SITE REQUEST (PHSC APP 1/6/93)
SUBMITTED 3/0/93; AMAITIHG HRC REVIEM 6, SHHPP 1
18 CFR 55.31, 55.59 APPROVAL.
HRR 81/86/93 Z(A 4
92G8239 2
SHHPP 1
HRR SITE REQUEST 85/28/92 Z(B SHHPP TSC - DC ELECTRICAL POMER SYSTEN SUBNITTED 6/29/92; HRC COISEHTS TO BE (PROVIDES ACTIOH STATENEHT TO ALLOM RESOLVED.
REVISED TSCR RECEIVED FROH HAVIHG BAllERY CHARGER OUT-OF-SERVICE)
HHP.
CORRESPOHDEHCE IH ROUTIHG.
(TSC 92-82) 92G8173 2
SITE REQUEST SNHPP NRR Sl/(5/92 Z1C SHNPP-lSC-GAS STORAGE TANKS (LIHIT QUANTITY OF RADIOACTIVITYIN EACH TANK FRON 1.85 E5 CURIES TO 86,825 CNIES)
TS 3.11.2.6 (TSC 92-81)
IHPUT RECEIVED.
PACKAGE IH ROUTIHG.
(AMAITIHG REG CNPLIANCE RESOLUllON OF CINEHTS).
93G8155 2
SNP TRIIITIOH SHNPP NRR 83/15/93 Z1D SHNPPlSC REVISE TABLE 3.9-1
'ADNIH CONTROLS TO PREVEHT DILUlION DURIHG REFUELIHG'O PROVIDE CLNIFICATIOH OH BOROH CONCENTRATION)
(HEEDED TO SUPPORT RFO 45)
A'MAITIHG HFS IHPUT.
93G8158 2
SHP TRANSITION QIPP 1
HRR 83/15/93 Z1n 4
SHHPPlSC-AXIAL FLUX DIFFEREHCE (REVISE TS 3.2.1 - REFEREHCES TO RAOC AHD BASE LOAD TO BE REPLACED BY PK-3 AFD TERNIHOLOGY.
(HEEDED TO SUPPORT RFO v5)
AMAITIHG HFS INPUT.
eh/28/93 CAROLIHA POMER l LIGHT CONPANY S
H H P P 18 NOHTH REGULATORY AGENDA ATT T 3 FACTS v SITE PRI SOURCE DOCUNEHT AGEHCY UNIT HUC PAI/SCH IHD ISSUE ACTIOH 93C8152 2
SHHPP HRA SHP TRAHSITIOH 83/15/93 Z(D QIPP TSC HEAT FLUX HOT CHANNEL FACTOR AMAITIHG HFS IKPUT.
REVISE lS 3.2.2 - CHANGE NETHODOLOCY AHD M(Z) lo V(Z)
(HEEDED TO SUPPORT RFO 45) 83/15/93 Z(D h
93G81h9 2
SHP TRA)SITIOH SHNPP 1
HRR QNPP-TSC~AE REACTIVITY BALANCE -
AMAITINC HFS IHPUT.
AEVISE TS h.1.1.1.2 (lO CORRECT A PARACRAPH AEFEREKCE)
(HEEDED TO SUPPORl RFO 45) 83/15/93 Z1D h
93C815h 2
SNP TRANSITION SHNPP 1
HRR SHHPP TSC SIENEHS NETHODOLOGY IH COLR AMAITIHG KFS IHPUT.
REVISE TS 6.9.1.6 - REFEREHCE (HEEDED TO SUPPORT RFO v5) 83/15/93 Z1D h
93G8151 2
SNP TRANSITION QIPP HAA QIPP TSC TARCET AFD - REVISE h.2.1.3 AND h.2.1.h TO NAXE TARGET AFD NORE ACCURATE AHD COHSISTEHT llITH PK-III NETHODOLOCY.
(HEEDED TO SUPPORT RFO 45)
AMAITIHG HFS IHPUT.
93C815V SHHPP KRR 2
SHP TRNSITIOH 83/15/93 Z(E h
QIPP-TSC-REVISE TS 2.2-1 REACTOR TRIP AMAITIHG HFS IHPUT.
SYSTEN IHSTAINEHTATIOH TRIP SETPOIHTS (HEEDED TO SUPPORT RFO 45)
84/28/93 CAROLIKA POMER 4 LIGHT CONPAHY S
H H P P - 18 NOHTH REGULATORY AGEHDA - ATT v 3 FACTS v SITE PRI SOURCE MCUNENT AGEHCY UNIT HUC PRI/SCH IHD ISSUE ACTIOH 84/13/93 ZIE 4
93G8214 2
SHP TRAHSITIOH SHHPP HRR SHHPP EDG START TINE TSC (TSC 93-
)
AMAITIHG KFS IKPUT.
83/15/93 Z1E 93G8153 2
SHP TRAHSITIOH SHHPP HRR SHNPP-TSC F DELTA H ACTIOH STATENENT AMAITIKG HFS IHPUT.
REVISE TS 3.2.3 TO ADDRESS EXCEEDIHG THE PEAKING FACTOR (HEEDED TO SUPPORT RFO 45) 93G8219 2
HED REQUEST SHHPP 1
HRR 83/22/93 ZIE SHNPP TSC-REVISE TS TABLE 3.3.4, ESFAS AMAITING KED INPUT.
TRIP SETPOIHTS TO IHCORPORATE UPDATED CALCS (BASED OH MESTIHGHOUSE GUIDAHCE) 91G8414 2
SHNPP 1
NRR SITE REQUEST 18/16/91 ZIE SHHPP-WGATIVE FLUX RATE TRIP DELETIOH TSC, ELINIKATIOHOF TRIP PER MESTING-HOUSE MCAP-11394-P-A (AN REQUESTED PRIOR TO RFO 45)
(TS 3/4.3.1)
(TSC 93-
)
HFS TO PROVIDE IHPUT.
SUBNITTAL TO COIHCIDE MITH TRAHSITIOH TO SIENEHS ANALYSES.
93G8213 2
SHHPP 1
NRR SITE REQUEST 84/13/93 ZIE SHHPP-RTD BYPASS TSC (TSC 93-
)
AMAITIHG HED IHPUT.
8h/28/93 CAROLINA POllER d LIGHT CONPANY S
H H P P - 18 NOHTH REGULATORY AGEHDA - ATT 4 3 FACTS vi SITE PRI SONCE DOCUKENT AGEHCY UHIT HUC PRI/SCH IHD ISSUE ACTIOH 93G8156 2
SHHPP 1
HRR SHP TRANSITION 83/15/93 Z1E h
SKKPP TSC REVISE TS FIGURE 2.1-1 REACTOR CORE SAFETY LINITS (HEEDED TO SUPPORT RFO ~5)
AMAITING HFS IKPUT.
88G8866 2
SHHPP SITE REQUEST 18/ih/88 Z2A 35 92G8229 2
SITE REQUEST, 18 CFR 58.68 SHNPP 1
HRR 85/13/92 Z2B h
SHHPPLINIIINGCOHDITIOHS FOR OPERATOR ACTION REQ'NHTS (ALLOMS Pi.ACIHG PLT IHTO A NODE MNERE TS IS HO LONGER APPLICABLE)
TS 3.1.2.2.3/3.1.2.h/3.7.1.1 (TS 87-12)
IHRC TAC 4 N79h18)
SHHPR-ISC-PltNE/TENPERATURE LINITS REV/S/ONS:
I REPLACENEHTS FOR 5 EfPY P/I Ll CURVES (BASED,OH L CAPSULE AHALYSIS)
SUBNITIED 12/28/98; AMAITIHG NRC REVIEM d APPROVAL. (PREHOIICED 2/28/91).
HRC REQUEST FOR ADDITIONAL ACTIOH REC'D 7/28/92; (RESPOHDED IO NRC'S RAI ON 9/29/92);
SUBNITTED 2/18/93,,(FORNAL RESP6(SE TO 1/29/93 KRC QUESTION) 8/25/93 HEED DATE BASED OH 188X THERNAL RUH IN CYCLE 5.
SUBMITTED 2/26/93.
AMAITING HRC REVIEM d'APPROVAL.
98G8318 2
HAD ORG.
CHANGE COHV.
SNKPP 1
MITH H.
BOMLES HRR 88/17/98 Z2C h
SHHPP-TECH SPEC CHANGE - HUCLEAR ASSESSNEHT DEPARTNEKT FUHCTIOHAI. CHANGES (INCLUDES POTEHTIAL TSC SAFETY REVIEMS)
(INTERNAL DUE DATE)
SUBNITIED 8/86/92.
AMAITIHG HRC REVIEM.
PREHOTICED 89/16/92.
~ l 15 wg'9G8515 SHHPP 1
HRR SITE REQUEST; GL 8941 1/31/89 (HRC-89-882) ie/29/89 Z2D SHKPP - RADIATIOH EFFLUEHT/EHVIROHKEHTAL
-SUBNITTED 7/21/92; SUBNITIED REVISED IS NONIIORIKG (RENOVAL OF TABLES FRON TS)
PAGES 9/3/92.
REQUESTED OH 12/18/92 THAT ISC 87-Sh (ORIG HLS-88-83h DTD 2/16/88)
KRC HOLD ANENDNEKT UllTIL 18CFR28 GEHERIC TS 3.3.3.18/3.11.1.1 GUIDANCE IS INCORPORATED IHTO TSCR.
SUPPLENEHTAL SUBNITTAL IH PREPARATION.
84/28/93 CAROLINA POMER 6 LIGHT CONPAHY S H H P P - 18 l10HTH REGULATORY AGEHDA - ATT 0 3 FACTS 8 SITE PRI SOURCE DOCUNEHT AGEHCY UNIT HUC PRI/SCH IHD ISSUE ACTIOH 92G8488 2
SHHPP HRR SITE REQUEST 88/26/92 Z2E SHHPPAREA:TENPERATURE NOHITORIHG TSC (IHCREASE TENP LINIT IK STEAN TUHHEL AND ADD AREAS OF PLAHT CURREHTLY HOT IH TS)
(TSC 92-83)
NLS PURSUIHG RELOCATION OF TS Tg PLANT PROCEDURES PER KUREGr1431.
89G8516 2
MCAP-18272-A SUPP 2, REV 1
SHKPP 1
HUREG 1431 NRR 85/e)r 89 Z2F 18 SHNPP-ESFAS SURVEILLANCE TESTING (TSC TO IHCREASE ALLOMED OUTAGE TINES (,
SURVEILLAHCE IHTERVAL FOR ESFAS IHSTRU-NEHTATIOH).
(TS 3.3.2)
(TSC 89-
)
PLAHT ASSESSIHG COST/BENEFIT OF CHANGE IH LIGHT OF MCAP AND ISSUANCE OF HEM INPROVED TS.
89/18/92 Z2G 4
92G8483 2
18 CFR 58.54(A)(3)
SHKPP HRR SHHPP-HRC APPROVAL OF QA PROGRAN CHAHGES SUBKITTED 8/6/92; AMAITIHG KRC REVIEM a APPROVAL.
93G8832 2
HRC-93-8813 GL 92-88 SHHPP 1
KRR 12/17/92 Z3A 4
SHHPP-GL 92-88 THERNO-LAG 338-1 FIRE LETTER IK RWTIKG.
BARRIERS 92G8534 2
HRC-92-8663 KRC RAI SHHPP HRR 11/25/92 Z3B 4
SHHPP-REQUEST FOR ADD'L IHFOR)(ATIOK-REGARDIHG REVIEM OF THE OFFSITE DOSE CALCULATION NAHUAL:
(NISC QUESTIONS BASED OH NRC REVIEM OF SEVERAL ANNUAL" ODCN SUBNITTALS)
DRAFT IKPUT REC'D.
FIHAL IKPUT AMAITING FEEDBACK FRON NRC STAFF REVIEMERS.
A
84/28/93 CAROLIHA POKER 6 LIGHT CONPAHY S H H P P - 18 NOHTH REGULATORY AGEHDA - ATT 4 3 FACTS 4 SITE AGEHCY PRI SOURCE DOCUNEHT UHIT HX PRI/SCH IHD ISSUE ACTION 92G8258 2
- 1KFR58, APPEHDIX E, PART F SHHPP SUBNIT GOALS 6 OBJECTIVES SHHPP 1
FOR 1993 FULL SCALE EXERCISE TO HRC HRR 86/16/92 Z3C SUBNITTAL REQ'D 75 DAYS PRIOR TO EXERC.
(EXERCISE SCHEDULED 1/27/93).
92G8113 2
SHHPP HRR Z3D SHHPP-ANNUAL FSAR ANEHDNEHT HO. 44 ANEHDNEHT hh PREPARATIOH IS IH PROGRESS.
EHGIHEERIHG DRAKIHGS ORDERED FRON SITE OH 3/19/93.
92G8268 2
- 18CFR58, APPEHDIX E, PART F SilPP SUBNIT SCEHARIO 6 CONTROLLER IHFO SUBNITTAL REQ'D 45 DAYS PRIOR TO EXERC:
S}NPP FOR 1993 FULL SCALE EXERCISE TO HRC (EXERCISE SCHEDULED 7/27/93).
HRR 87/15/92 Z3E 92G8373 2
18 CFR 58.46(A) (3) (II)
SHHPP HRR 88/27/92 Z3F QNPP-SUBNIT AHHUAL ECCS EVALUATIOH NODEL CHANGE REPORT (IH ACCORDANCE KITH 18 CFR 58.46 (A)(3) (II)
SUBNIT AHHUAl. ECCS EVAL NODEL CHANCES.
93G8128 1
SHHPP HRR 1KFR26.11(D)
Z3G SHHPP:
SENI AHHUAL FITHESS FOR DUTY REPORT DUE 68 DAYS FRON EHD OF RQORTIHG PERIOD.
84/28/93 CAROLINA POMER b LIGHT CONPANY S H H P P - 18 HOHTH REGULATORY AGENDA - ATT 4 3 FACTS v SITE PRI SOURCE DOCNEHT AGEHCY UNIT HUC PRI/SCH IND ISSUE ACTION 89G8542 2
CPLL LTR (NLS-89-298)
SHHPP HRR 18/31/89 Z3H 4
SHHPP-GEHERIC LETTER 88-28; IHDIVIDUAL PLANT EXANIHATIOH FOR SEVERE ACCIDEHT VULHERABILITIES ((eCFR58.54(F)
CHS PREPARIHG.
CPKL SUBNITTAL DATE REVISED PER HLS-91-888 DATED 3/21/91 12/84/92 Z3I 92G8569 1
HRC-92-784 QNPP HRR RESPOHSE TO BULLETIN 92-81, SUP 1.,
FAILURE OF THERHO-LAG 338 FIRE BARRIER
- SYSTEN, HHP INFORN NRC NEH FIRE BARRIERS ARE ACCEPTABLE.
~l 18/15/92 Z3J 93C8839 1
HLS-92-285 SHHPP HRR QNPP:
SUBHIT IPEEE AHALYSIS TO NRC 98G8884 5
SIlE REQUEST SHNPP 1
87/18/98 Z5 4
92G8886 5
HED REQUEST QNPP 88/28/92 Z5 4
SHNPPRAB/FHB ENERGEHCY EXHAUST HVAC (REVISE RAB 6 FHB HVAC TSC TO NATCH CR HVACTS)
)
QNPP-TSC - RTD BYPASS ELININATION TK-AVAITINGPLT IHPUT.
Aa
~ P ANITIHG HED IHPUT AHD PRIORITY FRON SITE.
64/26/93 CAROLIHA POMER b, LIGHT COKPAHY S H H P P - 18 KOHTH REGULATORY AGENDA - ATT v 3 FACTS ~
SITE PRI SOURCE DOCUKENT AGEHCY UHIT HUC PRI/SCH IND ISSUE ACTIOH 96G6231 5
SNNPP HRR SITE REQUEST e~/2V/96 Z5 14 SHHPP POTENTIAL TSC TO CLARIFY ULTIKATE,AMAITIHG SITE INPUT BASED OH PCR 5342 HEAT SIHK SPEC 3/4.7.5 ACTIONS (PCR DEVELOPKEHT 4 SCHEDULE TO BE ESTABLISHED).
(TSC 96-
)
6h/ih/96 Z5 4
96G6221 5
SITE REQUEST SHHPP 1
HRR SHHPP COHTAIHKEHT LIHER TEKPERATURE (REVISES DESIGN FEATURES SECTIOH TO REFERENCE LINER TEKP VS.
PEAX AIR TEKP)
TS 5.2.2 (TS 96-
)
TECH SPEC CHANCE; AMAITIHG PLANT IKPUT.
89G6536 5
SITE REQUEST SHKPP 1
HRR 63/18/88 Z5 4
SHNPP KOLDED CASE CIRCUIT BREAKERS (COHTAIHKENT PEKETRATIOH CONDUCTOR OVER-CURREHT PROTECTIOH TEST REVISIOH)
TSC 88-12 TS 4.8.4.1 TECH.
SPEC CHANGE.
AMAITIKG PLAHT APPROVAL OF PCR 2465, REV 6.
93G6158 5
SHHPP HRR HFS REQUEST 63/12/93
Z5 SHHPP-TSC - AFM: REVISIOH OF BASES TO CLARIFY FLOMRATE REQUIREKENTS AHD APPLICABLE ANALYSES AMAITIHG KFS INPUT.
91G6415 5
SITE REQUEST SHKPP HRR 16/11/91 Z5 4
SHHPP-DIESEL GEHERATOR SLUM START TESTING TSC (TS 3.8.1.1)
AMAITIHG SITE IKPUT AND PRIORITY.
'L CAROLINAPOWER 8a LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT PRESENTATION
.TO THE NRC ON
~ p.
SHEARON HARRIS CYCLE 6 ACTIVITIES ilgwu tO., P
~ ~
APRIL 22, l993
AGENDA INTRQDUGTzoN AND PURPosE LEwzs RowELL CURRENT PLANT STATUS LEwxs Mn.LS PLANNED ACTXVXTXES FOR CYCLE 6 LEWIS WELLS TRANsxTxoN To SPG ANAI.YSIS ACTIVITIES LzcKNsING AGTzvzTXEs
~ J Layzs RowEu.
APPROACH
TEcHNIcAL SPEGII:IcATIQN CHANGEs SUNQLRY LEwzs RowE~L
INTRODUCTION PURPOSE:
TO UPDATE THE NRC ON CP&L'S-PLANS FOR UPCOMING SHEARON HARRIS CYCLE 6 ACTIVITIES SUCH THAT NRC PLANNING AND SUPPORT IS FACILITATED.
~f H
- s a
CURRENT PLANT STATUS CYCLE 5 THIRD RELOAD OF MESTINGHOUSK VANTAGE 5 FUEL
-150 EFPD INTO THK CYCLE (436 EFPD CYCLE)
SHUTDowN oN 3/5/94 CORK OPERATING LIMITS REPORT (COLR) f~
K(z) 2.45 F~
1.65 AFD. RAOC; BASK LoaD M(Z)
NTC RXL BORON CONCENTRATION DURING REFUELING OPERATIoNs
PLANNED ACTIYITIES FOR CYCLE 6 TRANSITION TO SPC TRANSITIONING TO SIEMENS POL4KR CORPORATION AS FUEL SUPPLIER FOR CYCLE 6 - APRIL 1994 HIGHER BURNUP LEAD TEST ASSEMBLIES (8)
~ 62,000 MMD/NTU PEAK PIN IN'YCLE 8
~I<<<< '3($
~ % t>>
HIGHER THERMAL LIMITS 2.52
~ <<~ ~ CV+r =
~
~ ">4 F
N 1.66 1.73
<<'<<pl <<'g 5 t<<>>,y }~raiz
PLANNED ACTIYITIES FOR CYCLE 6 TRANSITION TO SPC POTENTIAL PLANT MODIFICATIONS RTD BYPASS ELIMINATION NEGATXVE FLUX RATE TRIP DELETION THpy REDUCTX ON
~ ~ ~
}e}
s'/G HI-HI LEVEL.TRIP. TOTAL Aa.LOWANCK INCREASE AND LOM=LOM LEVEL TRXP,SETPOZNT RKDUCTXON DZEsEL START TIxK INCRKasK HARDwARE (sHow HARDMARE) 4'".V'4q
g ~ '
eo I
PLANNED ACTIYITIES FOR CYCLE 6
~ \\
TRANSITION TO SPC FUEL DESIGN DESCRIPTION 17x17 HTP/IFH wITH FUELGUARD BURNUP LIMITS (PEAX, ROD &2t000 HMD/HTU)
CHANGES FROM LAST PRESENTATION 1
HELIUM FILL PRESSURE TO 370 PSIG CLAD sTRAIN LIMIT coNsIsTENT wITH SRP (1% STRAIN TO 60,000 MWn/HTQ AND 0.75%
ABOVE)
PLANNED ACTIVITIES FOR CYCLE 6 ANALYSIS ACTIVITIES SPC RELOAD ANALYSIS SUPPORT REANALYSIS OF BOUNDING CONDITION II EVENTS
- REANALYSIS OF CONDITION III AND IV EVENTS EXCEPT SGTR APPENozx>> K LBLOCA AND SBLOCA; NoN-LOCA TRANSIENTS AND SETPOXNTS; CRXTICALZTY; 5ROPPED ASSEMBLY NaW MKTHODOLOGXES REQUIRING NRC APPROVAL HTP DNB CORRELATION - EXTENSION OF APPROVED ANFP CORRKLATIQN STATISTICAL TRANSIENT MODEL -
EXTKNSZON OF APPROVED STATISTICAL METHODOLOGY-USED IN CK TYPE REACTORS REVISED SBLOCA MODEL - MODIFICATION TO EXZSTXNG APPENDIX K SBLOCA MODEL GENERIC 17X17 MKCHANXCAL DESIGN RKPORT-IJSKS APPROVED CODKS AND METHODOLOGY UP TO CURRENT BURNUP LZMIT
PLANNED ACTIVITIES FOR CYCLE 6 ANALYSIS ACTIVITIES ITEX-'.
PROPOSED SUBMITTAL DATE
'.'CTUAL';:;.'"...:'iP.ROVAL:.
SUBNITTAL'>:,.".'."- ',".,".,
DATE'. ""'"'=.
RODEX3 APPRQYAL (FOR REALZSTZC LOCA)
REvIsED SBLOCA MoDEL STATISTICAL TRANSZENT METHODOLOGY Mav 1991 MAv 1991 OCT 1993 MAv 1992 MAv 1992 AuG 1993 Mav 1992 MAY 1992 Aus 1993 HTP DNB CORRELATION SEP 1992 SEP 1992 JUL 1993 REALISTIC LOCA METHODOLOGY (NOT FOR CYCLE 6)
OCT 1992 SEP 1992, OCT 1992, DEc 1992, JUN 1993 (START OcT 1993 AND GO FOR -2 YEARS)
AUTOMATIC ROD CONTROL METHODOLOGY MECHANICAL DESIGN REPORT FEB 1993 HDT To IK REYIEMED BY THE NRC OcT 1993 APR 1993 DEC 1993 RELDAD ANALYSIs
~
SAFETY ANALYSIS REPORT
~
TRANSIENT 5 SETPOZNT ANALYSIS
~
LOCA ANALYSES DEc 1993 DEc 1993 NOTES:
CYCLK 5 PLANT SHUTDOMN - MARCH 1994 CYCLE 6 PLANT STARTUP APRIL 1994
\\
LICENSING ACTIVITIES APPROACH SUBMITTALS STRUCTURED TO FACILITATE NRC REVInt METHODOLOGIES SUBMXTTKD FOR NRC REVIEW SUBMITTAL OF LICENSE AMENDMENTS METHODOLOGIES OTHER CHANGES AS NECESSARY DRAFT CORK OPERATING LXMITS REPORT (COLR)
INCLUDED TO DEMONSTRATE USAGE UTILIZATXON OF COLR FOR CYCLE TO CYCLE CHANGES PER 10 CFR 50.59
LICENSING ACTIYITIES TECHNICAL SPECIFICATION 'CHANGES GROUP 1, (TS CHANGES TO BE SUBMITTED TO THE NRC BY e3UNE 15, 1993):
CORE REACTIVITY BALANCE REVISION TO PARAGRAPH REFERENCK TS 3.2.1 - AXXAL FLUX DIFFERENCE (AFD)
REFERENCES TO RAOC AND BASE LOAD OPERATION WILL BE REPLACED BY THE PDC-3 AFD TERMINOLOGY TS 4.2.1.3 AND 4.2.1.4
- TARGET AFD REVXSXON TO MAKE TARGET AFD DETKRMXNATXQN MORE ACCURATE AND CONSISTENT WXTH THK PDC-3 METHODOLOGY TS 3.2.2 - HEAT FLUX HOT CHANNEL FACTOR RAOC AND BASK LOAD TERMXNOLOGY WXLL BK REPLACED BY THE PDC-3 TKRMXNOLOGY'(Z)
WXLL BK CHANGED TQ V(Z)
TS TABLE 3.9 ADMXNXSTRATXVE CONTROLS PROVXDK CLARIFICATION ON BORON CONCENTRATION TS 6.9.1.6 -
CORE OPERATING LXMITS REPORT REFERENCE SECTION WILL SE CHANGED TO INCORPORATE SXEMKNS METHODOLOGY
LICENSING ACTIVITIES TECHNICAL SPECIFICATION CHANGES (CON'T)
GROUP 2
(TS CHANGES TO SE SUBMXTTKP TO THK NRC SY SEPTEMBER 1, 1993):
TS FIGURE 2.1 REACTOR CORK SAFETY LIMITS DRAFT CORE OPERATING LIMITS REPORT (CQLR)
POSSIBLE CHANGES:
TS TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SKTPOINTS DELETION OF THK TS 3.3.1 - HIGH NKGATIYK NEUTRON FLUX RATE TRIP TS 3.2.3 - THK F >
CHANGE TO F >" TO ACCOUNT FOR THE USK OF THE SIEMENS STATISTICAL MKTHOPOLOGYt REYISION To ACTION STATEMENT
SUh%QRY WE HAVE DISCUSSED:
CURRENT PLANr Srarus PLANNED ACTIVITIES FOR CYCLE 6 LICENSING ACTIVITIES SCHEDULE