ML20195E915
| ML20195E915 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain |
| Issue date: | 06/02/1986 |
| From: | Brey H PUBLIC SERVICE CO. OF COLORADO |
| To: | Berkow H Office of Nuclear Reactor Regulation |
| References | |
| P-86399, NUDOCS 8606090281 | |
| Download: ML20195E915 (9) | |
Text
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2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 June 2, 1986 Fort St. Vrain Unit No. 1 P-86399 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Attn: Mr. H.N. Berkow, Director Standardization and Special Projects Directorate Docket No.
50-267
SUBJECT:
Regulatory Information Tracking System
REFERENCE:
- 1) NRC Letter, Heitner to Walker, Dated May 2, 1986 (G-86241)
- 2) PSC letter, Brey to Berkow, dated May 28, 1986(P-86395)
Dear Mr. Berkow:
In Reference 1, the NRC requested that PSC review a list of Fort St.
Vrain-specific approved regulatory improvements and provide a status of each requirement. Reference 2 transmitted PSC's response to this request.
This letter provides a revision to Attachment 1 of Reference 2.
This revision incorporates an estimated fourth refueling completion date of June 1,1988.
8606090201 e60602 i
DR ADOCK OD00 7
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P-06399 Page 2 June 2, 1986 i
If you need further information on any item in this letter, or if you have any further questions, please contact Mr.
M.
H.
Holmes (303) 480-6960.
Very truly yours, i
w t
I H. L. Brey, Manager i
Nuclear Licensing and Fuels HLB /KP0:kb Attachment l
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Revision l' ATTACHMENT 1 to P-86399-l This attachment contains the list of approved regulatory action for which NRC requested completion / implementation dates at FSV.
The following information is given for each item:
MPA -
NRC MULTIPLANT ACTION NUMBER TAC -
NRC TAC NUMBER j
STATUS - ' STATUS OF ITEM - C - COMPLETE P - PROJECTED 1 - PSC DOES NOT HAVE THIS ITEM l
IDENTIFIED IN OUR TRACKING SYSTEM 2 - ALTHOUGH NRC CONSIDERS THIS ITEM COMPLETE, PSC HAS TIED ITS COMPLETION WITH SPDS IMPLEMENTATION (FOURTHREFUELING) 3 - ALTHOUGH THE REQUIREMENTS FOR THIS ITEM ARE ESS6NTIALLY COMPLETE, THE FINAL COMPLETION DATE IS TIED TO SPDS IMPLEMENTATION 4 -NRC HAS VERBALLY INDICATED THAT THIS ITEM IS ALMOST CERTAINLY NOT APPLICABLE TO FSV l
5 -PSC AND NRC, REGION IV, ARE 4
WORKING AT THIS TIME TO ARRANGE A MEETING TO DISCUSS THIS ISSUE i
SUBJECT - SUBJECT OF ITEM i
DATE -
COMPLETION DATE OR PROJECTED COMPLETION CL -
RELATED PSC COMMITMENT LOG NUMBER (S)
REF -
CLOSINGREFERENCE(S)OROTHERAPPLICABLEREFERENCE(S) i i
i 1
1 1
2
- - - - _ _. _ -, - -. _ _ - _ - _ _, _ ~ _,
Revision 1 to P-86399 Page 2 MPA TAC STATUS SUBJECT DATE CL REF A-02 M48341 C
RADIOLOGICAL ENVIRONMENTAL JAN. 1, RETS TECH SPECS (RETS) 1984 A-03 M06939 C
SECURITY PLAN 1978 0259 P-78056 A-10 M11576 C
CONTINGENCY PLAN 1981 0661 P-81149 A-11 M11577 C
GUARD TRAINING 1981 0645 P-81100 A-16 M47557 C
QUALIFICATION OF EXAMINATION, 1982 0697 GL 81-01 INSPECTION, TESTING P-82042 G-82098 A-17 M51092 P
POST ACCIDENT MONITORING FOURTH 1068A)B) G-85345 INSTRUMENTATION.
RE-1069A)B) P-85446 FUELING 1098 (EST.
1115
- JUNE, 1988)
A-18 M55710 C
TECH SPECS AFFECTED BY MAR.
0860 P-84068 GENERIC LETTER 83-43 1984 A-20 M59097 C
10CFR50.62 OPERATING REACTOR OCT.
1114 P-85368 REVIEWS 1985 B-16 M12155 C
EMERGENCY PLANNING, REVISIONS 1981 0534 P-80083 0677 P-82023 8-17 M47417 C
TECH SPEC SURVEILLANCE -
JAN.
G-84036 SNUBBERS 1984 B-23 M46504 C
DEGRADED GRID VOLTAGE 1976 0207 P-76215 G-86060 G-82338 (SER)
P-83161 G-83138 B-44 M30001 C
NUREG-0737 - 2.1.7.B CONTROL GRADE 1980 0529 G-79279 AUX. FEEDFLOW INDICATION P-80438 B-44 M30002 C
2.1.5.A, L, C DEDICATED HYDR 0 GEN 1980 N/A TO G-79279 CONTROL PENETRATIONS FSV B-44 M30004 C
2.2.2.A, B, C CONTROL ROOM 1980 0509 INTERNAL ACCESS, TECH SPEC SUPPORT CENTER, 0510 PROCEDURES OPERATIONAL SUPPORT CENTER 0511 P-79312 0512 0513 Revision 1
.to P-86399 Page 3 MPA TAC STATUS SUBJECT DATE CL REF B-44 M30005 C
2.2.1.A, B, C SHIFT SUPERVISOR,
- 1980, 0505 P-80444 SHIFT TECHNICAL ADVISOR,
- 1980, 0506 G-82080 TURNOVER PROCEDURES
- 1985, 0507A)
G-85405 0508 P-86013 B-44 M30006 C
2.1.8.C IMPROVED I0 DINE INST.
1980 0504A)
INTERNAL MEM0 B-44 M30007 C
2.1.8.B HIGH RANGE RADIATION 1979 0503A)
P-79312 B-44 M30008 C
2.1.8.A POST ACCIDENT SAMPLING 1979 0501C)
P-79312 B-44 M30009 C
2.1.6.B SHIELDING REVIEW 1979 0501A)
P-79312 B-44 M30010 C
2.1.6.A SYSTEMS INTEGRITY FOR 1979 P-79299 HIGH RADI0 ACTIVITY B-44 M30011 C
2.1.4 DIVERSE CONTAINMENT 1980 N/A TO P-79299 ISOLATION FSV P-80028 B-44 M30012 C
2.1.3.B INSTRUMENTATION FOR 1980 G-80049 CORE COOLING B-44 M30013 C
2.1.3.A DIRECT INDICATION OF 1980 N/A TO P-80028 VALVE POSITION FSV 0539 B-44 MJ0014 C
2.1.2 RELIEF AND SAFETY VALVE 1980 0539 P-80028 TESTING B-48 M46503 C
ADEQUACY OF STATION ELECTRIC 1982 0582A)
P-82169 DISTRIBUTION V0LTAGE G-82265 B-59 M42925 C
MASONRY WALL DESIGN JAN.
VARI.
G-86035 1986 084E P-83364 B-60 M42527 P
ENVIRONMENTAL QUALIFICATION VARI.
VARIOUS B-62 M2743 C
IE BULLETIN 80 ESF 1982 0692 G-82338 RESET CONTROL DESIGN P-82054 B-63 M43935 C
GENERIC LETTER 81-04 PROCEDURES 1982 0650A)B) P-81207 FOR SHORT TERM BLACK 0UT G-82264 B-70 M46617 4
FATIGUE TRANSIENT LIMITS FOR N/A TO REACTOR COOLING SYSTEM FSV B-76 M52759 C
ATWS 1.1 POST-TRIP REVIEW JUNE 1145 G-85114 PROGRAM DESCRIPTION & PROCEDURE 1985 P-83359
a Revision 1
.to P-86399 Page 4 MPA TAC STATUS SUBJECT DATE CL REF B-77 M52840 C
ATWS ITEM 2.1 - EQUIPMENT MAY 1283 P-83359 CLASSIFICATION & VENDOR INTERFACE 1986 P-85204
- RTS COMP 0NENTS B-78 M52921 C
ATWS ITEM 3.1.1 AND 3.1.2 -
MAY 1145 P-85204 POST MAINTENANCE TESTING PROCEDURE 1986 INTERNAL PROCEDURES B-79 M53002 C
ATWS 3.1.3 - POST MAINTENANCE JUNE 1125G)
P-85204 TESTING - CHANGES TO TS 1985 B-83 M54535 C
TECH SPECS C0VERED BY GLs DEC.
0853A P-84046 83-36, 83-37 FOR NUREG 0737 1985 0878E P-85481 B-85 M53591 C
ATWS 1.2 POST-TRIP REVIEW DATA JULY 1145 G-85296 CAPABILITIES 1985 B-86 M53674 C
ATWS 2.2 EQUIPMENT CLASSIFICATION MAY 0851 P-85204
& VENDOR INTERFACE - ALL SR COMP 0NENTS 1986 1283 B-87 M53757 C
ATWS 3.2.1 & 3.2.2 - SR MAY 1145 P-85204 COMPONENTS - PM TESTING, VEND 0R, 1986 RECOMMENDATIONS B-88 M53840 C
ATWS 3.2.3 SR COMPONENTS MAY 1145 P-85204 CHANGES T0'T.S.
1986 B-92 M54067 1
ATWS 4.5.1 DIVERSE TRIP FEATURES NOV.
0818 P-83359 1983 B-93 M53984 1
4.5.2, 4.5.3 ALTERNATIVES AND TEST NOV.
0818 P-83359 INTERVALS 1983 C-10 M11025 C
CONTROL 0F HEAVY LOADS OVER MAR.
G-84075 SPENT FUEL P00L NUREG 612 1984 C-15 M52230 C
OCT.
10718)C)P-85361 PHASE II 1985 G-85254 C-16 M58061 C
UTILITY RESPONSE TO NRC RECOMMEND-JULY 1146 P-85244 ATIONS RE: STEAM GENERATORS (GL-86-02) 1985 D-19 M55861 C
DIESEL GENERATOR RELIABILITY AUG.
0923 P-84501 TECH SPECS (GL-84-15) 1985 G-85368 F-01 M44022 C
TMI I.A.1.1 SHIFT TECHNICAL MAR.
0585A)C)P-80444 ADVISOR 1982 G-82080 i
Revision 1
.to P-86399 Page 5 MPA TAC STATUS SUBJECT DATE CL REF l
l l
F-02 M44091 C
I.A.1.1 SHIFT MANNING MAR.
0586A)C) G-83369 l
1983 0651A)B) l l
F-03 M44163 C
I.A.2.1 UPGRADE SR0 & R0 MAR.
0587 P-81002 TRAINING 1982 G-82084 G-82084 F-04 M44234 P
I.C.1.2/3.A E0PSD - INADEQUATE 4th RE-1126J)
P-86331 l
CORE C0OLING GUIDELINE FUELING l
(EST.
l
- JUNE, j
1988)
F-05 M44304 P
I.C.1.2/3.B PROCEDURES 4th RE-1121B)
P-85386 GENERATION PACKAGE (PGP)
FUELING G-85345 i
l (EST.
- JUNE, i
l 1988)
F-06 M47217 C
I.C.5 FEEDBACK 0F OPERATING MAR.
0564A)
G-82084 EXPERIENCE 1982 0589 INTERNAL MEMO F-07 M47289 C
I.C.6 CORRECT PERFORMANCE SEPT.
0619 P-82424 0F OPERATING ACTIVITIES 1982 G-82370 F-08 M51162 C
I.D.1.1 DETAILED CONTROL ROOM AUG.
1218 P-85454 DESIGN REVIEW (DCRDR) 1985 F-09 M51242 P
I.D.2. SAFETY PARAMETERS 4th RE-0975 G-85345 DISPLAY SYSTEM (SPDS)
FUELING VARI.
(EST.
- JUNE, 1988)
F-10 M44375 C
II.B.1. REACTOR COOLANT SYSTEM MAR.
.0593 P-80438 (RCS) HIGH POINT VENTS 1982 G-82084 F-11 M47940 C
II.B.2 PLANT SHIELDING MAR.
0594 P-80438 1983 0595 G-83117 F-12 M44443 C
II.B.3 POST ACCIDENT JAN.
1202 G-86028 SAMPLING 1986 AND P-85446 OTHERS F-13 M45345 C
II.D.I. RELIEF VALVES MAR.
N/A G-82084 VALVES AND SAFETY VALVES 1984 TO TRAINING FSV Revision 1 to P-86399 Page 6 MPA TAC STATUS SUBJECT DATE CL REF F-18 M44781 C
II.E.4.1. DEDICATED HYDR 0 GEN MAR.
N/A G-82084 PENETRATIONS 19, to 1984 FSV F-19 M44852 C
II.E.4.2. CONTAINMENT ISOLATION MAR.
N/A G-82084 DEPENDABILITY 19, TO 1984 FSV F-20 M57944 P,2 II.F.1.1 N0BLE nS MONITOR 4th RE-0967 P-84506 FUELING 0985 P-85174 (EST.
0908 G-86028
- JUNE, (G-86028 1988)
DATED 1/9/86 SAYS II.F.1.1 I@
COMPLETE)
F-21 M44994 C
II.F.1.2 I0 DINE / PARTICULATE MAR.
EXISTING G-82084 SAMPLING 1982 EQUIP.
WAS DEEMED SUFFIC-IENT.
F-22 M45065 C
II.F.1.3 CONTAINMENT MAY 0878B)
G-84164 HIGH RANCE MONITOR 1984 F-23 M47601 C
II.F.1.4. CONTAINMENT MAR.
N/A G-82084 PRESSURE INSTRUMENT 1982 to FSV F-24 M47672 C
II.F.1.5 CONTAINMENT MAR.
N/A G-82084 WATER LEVEL INSTRUMENT 1982 TO G-82084 FSV F-25 M47743 C
II.F.1.6 CONTAINMENT MAR.
N/A G-82084 HYDROGEN MONITOR 1982 TO FSV F-26 M45136 C
II.F.2 INADEQUATE CORE MAR.
ALREADY G-82084 C0OLING INSTRUMENT 1982 SUFFI-CIENT AT FSV F-38 M45345 C
II.K.3.3 REPORTING SAFETY VALVE MAR.
N/A G-82084 AND RELIEF VALVE FAILURES 1982 TO AND CHALLANGES FSV F-47 M45632 C
0565 G-82084 1982
i Revision H
.ta P-B6399 Page 7 MPA TAC STATUS SUBJECT DATE CL REF F-57 M45828 C
II.K.3.30 SMALL BREAK LOCA MAR.
N/A G-82084 j
METHODS 1982 TO FSV F-58 M48167 C
II.K.3.31 COMPLIANCE WITH MAR.
N/A G-82084 10 CFR 50.46 1982 TO FSV F-63 M45947 P,3 II.A.1.2 TECH SUPPORT 4th RE-0606A)B) P-83147 CENTER FUELING 1155 (EST.
- JUNE, 1988)
F-64 M46018 C
II.A.1.2 OPERATIONAL 1983 0606A)B) P-83147 SUPPORT CENTER 1155 F-65 M46090 P,3 III.A.1.2 EMERGENCY 4th RE-0606A)B) P-83147 OPERATIONS FACILITY FUELING 1155 (EST.
- JUNE, 1988)
F-66 M46162 5
II.A.1.2 NUCLEAR DATA LINK -
G-86111 EMERGENCY RESPONSE DATA SYSTEM (ERDS)
F-67 M46234 C
II.A.2.2 EMERGENCY PLAN JUNE 07750)
G-83249 UPGRADE TO MEET RULE 1983 P-83178 F-68 M46306 P,3 II.A.2.2 METER 0 LOGICAL 4th RE-0664 G-82163 DATA UPGRADE FUELING (EST.
- JUNE, 1988)
F-69 M46377 C
III.D.3.3 INPLANT MAR.
0609 G-82084 RADIATION MONITORING 1982 P-80444 F-70 M46448 C
II.D.3.4 CONTROL ROOM SEPT.
VARI.
G-83333 HABITABILITY 1983 F-80 M56125 P
I.D.I.2 DETAILED CONTROL AFTER 07988)
P-86205 ROOM DESIGN REVIEW
SUMMARY
4th RE-1155 REPORT FUELING 1156 (EST.
- JUNE, 1988)