ML20245E671
| ML20245E671 | |
| Person / Time | |
|---|---|
| Issue date: | 12/22/1988 |
| From: | Butcher E Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8901130134 | |
| Download: ML20245E671 (8) | |
Text
V UNITED STATES I
-u
'o NUCLEAR REGULATORY COMMISSION n
- j wAssiwaTow, p. c. aosse 1.
%..'....o#
DEC 2 21988
~ MEMORANDUM FOR:
Charles E. Rossi Director Division of Operational Events Assessment, NRR FROM:
Edward J. Butcher, Chief Technical Specifications Branch Division of Operational Evente Assessment. NRR
SUBJECT:
MINUTES OF MEETING WITH NUMARC TASK GROUP WHICH IS WRITING NEW STS FOR INSTRUMENTATION On Thursday, October 20, 1988, the staff met with the NUMARC task group which is writing the new Standard Technical Specifications (STS) instrumentation sections to hear their early estimate of anticipated technical changes. The staff was also interested in discerning any technical change that might require a review effort outside the normal STS review process.
The owners groups commented that the following technical changes are to be proposed with the new STS:
1.
Various requirements are to be reorganized and relocated within technical specifications.
A.
Limiting Scfety System Settings are to be relocated from section 2 of the technical specifications to the specifications for the reactor protection system.
B.
Response times are to be relocated from the instrumentation section to section 5 of the technical specifications. However, requirements to meet specified response times are to remain in the applicable LCO's.
C.
Tables (other than response time tables) in the Reactor Trip System Instrumentation and the Engineered Safety Feature Actuation System sections are to be combined into a single table.
2.
Specific instrumentation requirements are to be relocated as follows:
A.
Most Radiation Monitoring Instrumentation specifications for PWR's are to be relocated within technical specifications with the system related to the instrument or with RETS, as applicable. See enclosed instrumentation table of contents for typical PWR's. All instrumen-tation specifications for BWR's are to be located in a single instru-mentation section.
B.
The owners groups propose that the following two specific Radiation
[I Monitoring Instrumentation specifications be relocated outside of 1/
technical specifications.
]l (b ' Criticality monitors.
(g4 l
(2) Containment radiation area, high range.
(U 8901130134 881222 i
- PDR REVGP ERGNUMRC PDC -
DEC 2 21soo m
.1 L 2,.' '
~t
^
y The. owners groups are to provide technical. justification,~in their-submittals, that this instrumentation does.not meet the interim policy statement's criteria for re% ntion in technical specifications.
C.
Specific Accident Monitoring' Instrumentation requirements are to be-relocated outside of technical-specifications.. See enclosed " Table 3.2.3-1, ACCIDENT-MONITORING INSTRUMENTATION," for the generic set of Accident Monitoring Instrumentation to be retained. This set is to be augmented on a plant specific basis.
The owners groups asked if the staff had a position on any, other than the 7 listed, Category.1 variable's being risk significant and, therefore, being retained in technical specifications. The staff responded that the ouestion is not which Category 1 variables are risk significant and;should be retained in technical specifications, but rather which Category 1. variables,.if any, are not risk significant and could be relocated from technical specifications. The staff reiterated its position that the Owners Groups would have to provide analyses to justify that a Category 1 variable is not risk significant and, therefore, could be relocated from technical specifications.
D.
Remote Shutdown Instrumentation' specifications are to be' relocated to -
the Fire Protection Program or other licensee controlled document.
See enclosed instrumentation table of contents for typical PWR's.
The staf t cautioned the owners groups that while the relocation of Remote Shutdown Instrumentation specifications outside of technical specifications was being discussed by the staff, the published staff position remained that these instrumentation requirements would remain in technical specifications.
E.
RCS Leakage Detection Instrumentation requirements are to be relocated within technical specifications to the Reactor Coolant System section.
See enclosed table of contents for typical PWR's.
The owners groups consnented that while other technical changes could develop, the above are the most significant ones known at the time of the meeting.
With respect to situations where proposed technical changes are of the nature of relocating technical specification requirements outside of technical specifi-cations, the staff position is presented in the " split report"; see NRC letter The staff does not anticipate from T. E. Murley to R. A. Newton, dated May 8,1988.
revisiting these issues.
V DEC 2 21988 2
The owners groups are to provide technical justification. in their submittals.:that this instrumentation does not meet the interim j
policy statement's criteria for retention in technical specifications.
C.
Specific Accident Monitoring Instrumentation requirements are to be relocated outside of technical specifications. See enclosed " Table 3.2.3-1. ACCIDENT MONITORING INSTRUMENTATION.". for the generic set of.
Accident Monitoring Instrumentation to be retained. This set is to be-i augmented on a plant specific basis.
The owners groups are to provide analyses to justify based on risk..
relocation of specific instruments out of technical specifications.
D.
Remote' Shutdown Instrumentation specifications are to be relocated to the Fire Protection Program or other licensee controlled document.
See enclosed instrumentation table of contents for typical PWR's.
The staff cautioned the owners groups that while the relocation of Remote Shutdown Instrumentation specifications outside of technical specifications was being discussed by the staff, the published staff position remained that these instrumentation requirements would remain in technical specifications.
E.
RCS Leakage Detection Instrumentation requirements are to be relocated within technical specifications to the Reactor Coolant System section.
See enclosed table of contents for typical PWR's.
The owners groups commented that while other technical changes could develop, the above are the most significant ones known at the time of the meeting.
The staff did not identify any technical change which would constitute either of the following:
(1) A change in addition to proposed changes already under staff consideration, or (2) A change which would require a review effort outside the normal STS review process.
Edward J. Butcher Chief Technical Specifications Branch j
Division of Operational Events Assessment. NRR
Enclosures:
As stated DISTRIBUTION:
Please see attached 4
9 (MIG.
INUTES/10/20/88 MARK)
)
pN1 TSB:00EA:NRR TSB:00EA:NRR C: CB:N R C:PR V
C:TSB:00EA:NRR v4/tf FMReinhart:pmc DCFischer SNewberry RJBa t
EJButcher 11/
88 11/ /88 INhb 11/D/88 11/16/88 11/q88
l s
DEC 2 219BB
., Except relocation issues, which are addressed in the preceding paragraph, the staff did not identify any technical change which would constitute either of the following:
(1)Achangeinadditiontoproposedchangesalreadyunderstaff consideration, or (2) A change which would reouire a review effort outside the normal STS review process.
Original Signed by David C. Fischer pv' Edward J. Butcher, Chief Technical Specifications Branch Division of Operational Events Assessment, NRR
Enclosures:
As stated DISTRIBUTION:
Please see attached I
(MTG. MINUTES /10/20/88 PARK)
{
(*See previous concurrence)
'd
)
- TSB:00EA:NRR
- TSB:D0EA:NRR *C:SICB:NRR
- C:PRAB:NRR C:TSB:00EA:NRR FMReinhart:pmc
.DCFischer SNewberry RJBarrett EJButcher 11/22/88 11/16/88 11/29/88 11/30/88 12/q/88
- SRXB:NRR kNodges 12/20/88 u
N lypact (L)R
. Attachment 1 INSTRUMENTATION TABLE OF CONTENTS LCO No.
TITLE PAGE NO.
3.2.1 Reactor Trip System Instrumentation 3.2-1 3.2.2 Engineered Safety Features Actuation System 3.2-25 0.2.b n;di;tierAlor4toring In:trum:nt: tier.
3.20 3.2.4 Accident Monitoring Instrumentation 3.2-52 atstion 3.2 55 3.f.5 0;;;te St"idown In:('r;;Rtsa6m dcyauncr rtxr cto.+ot el tt ttuoxnf Wruu. < a 0.2.0 000 k-'k;;; Oct ct';n In:tru;;nt;ti;n 3.2-50 k auas rc liu butsta BASES BASES No.
TITLE PAGE No.
B 3.2.1 Reactor Trip System Instrumentation B 3.2-1 8 3.2.2 Engineered Safety Features Actuation System B 3.2-44 0 0.2.3 nadietion ".;;it; ring In:tre nt: tier
? ? ?-99 B 3.2.4 Accident Monitoring Instrumentation B 3.2-93 0 3.2.5 n;;;te Shutd;wn Instrumentatier S 3.0 100 -
O 0.2.0 000 L :k;;; Oct:ctier In:trum:ntier S 3.2 117 l
L__.______________
' k *;
l
. - ~
Lv
, p.
Accident Monitoring
[l.;
3.2.3 TABLE 3.2.3.-1 ACCIDENT MONITORING INSTRUMENTATION Steam Generator Pressure Steam Generator Level [ Range)
- Bcrated Water Storage Tank Level' [ Range]
Upper Surge Tank' Level (Condensate Storage) [ Range)
RCS Subcooling Margin Unit Name 3.2-74 Amendment Draft 3 10/12/88
~.
A 0::tober 31,1988 Enclosure (3)
MRETIl0 ATI' ENTE tjage Affiliation James G.- Lahti Westinghouse Stewart Webster Combustion Engineering Peter W. Smith SCE.
Jerry C. Jones.
' Robert Gill Duke Power Jack Stringfellow SCS-Jacquie Ilinde IGE Walt Smith NUMARC George Smith Westinghouse-Courtney Smyth GPU Nuclear IMR OG Rob Woolley GAISC-SPEC-SERVICES David Fischer NBC/NRR/0TSB Mark Reinhart NRC/NPR/CfrSB Millard Wohl NRC/NRR/CTFSB Tom Dunning NRC/NRR/0rSB-Kulin Desai NRC/NRR/0TSB Frank Ashe NRC/OSP/CPPD Barry Marcas NRC/NRR/SICB Sarmy Diab NBC/NRR/PRAB Chu-yu Liang NRC/NRR/SRXB
- o
- y 2
4 DEC 2 21988 015TRIBUTION:
~~
f0ROTSEP] Members TEMurley JHConran JHSniezek CHBerlinger FJMiraglia' W0Lanning OTSB R/F
- DMCrutchfield JLieberman. OE 00EA R/F SAVa rga.
LShao' Central Files BKGrimes JWRoe JGPer* low. OSP ELJordan. AE00 FJCongel C1 Grimes FGillespie HLThompson Jr. NMSS Regional Administrators GHolahan MMalsch NRC Participants SDRichardson-WGKennedy OTSB S/F - (MEETING NOTICE) s i
I
- _ _ _ _ - _ - _ _ _ _ _ _ _ - _ _ _