ML20043H752
| ML20043H752 | |
| Person / Time | |
|---|---|
| Issue date: | 12/12/1989 |
| From: | Fraley R Advisory Committee on Reactor Safeguards |
| To: | Blaha J, Taylor J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| References | |
| REF-GTECI-087, REF-GTECI-NI, TASK-087, TASK-87, TASK-OR ACRS-GENERAL, GL-88-20, NUDOCS 9006260401 | |
| Download: ML20043H752 (8) | |
Text
,-
hh
'o UNITED $TATES 1
NUCLEAR REGULATORY COMMISSION -
t "l'
ADVISORY COMMITTEE ON REACTOR SAFEGUARD 6 wAsHwatow. o. c.rosos
....+
December 12, 1989 1
i MEMORANDUM FOR: James M.' Taylor i
L Executive Director for Operations-1 1
ATTN:
J. Blaha
]>. ss FROM:
R. u ey, e @ ve Director,'ACRS
SUBJECT:
355TH ACRS MEETING' FOLLOW-UP ITEMS-t Based on discussions regarding methods-for improved implementation and-5 follow-up of ACRS reconnendations,- the Committee agreed that a -summary of.
Actions, Agreements, Assignments, and Requests made during each full Connittee meeting will' be sent to your office following each meeting.-
' Attached per this agreement is a list of the requests made at the 355th-ACRS Meeting, November 16-18, 1989.
l
Attachment:
I-As stated cc w/att:
E. L. Jordan, AE00 R. M. Bernero, NMSS T. E. Murley, NRR E. S. Beckjord, RES S. Chilk, SECY.
- A. : Vietti-Cook. OCN/KC C. Ader,'0CM/TR G. Marcus, OCM/KR D, Trimble. OCM/JC i
F. Remick,-0CM
-l l
i r
f:
1 4
DESIONATED ORIGIRAls go626ogot g, g E
Certified BF L
f ACTIONS, AGREEMENTS, ASSIGNMENTS, REQUESTS,-
AND
SUMMARY
OF FOLLOW-UP MATTERS
'355TH ACRS MEETING NOVEMBER 16-18, 1989 l
REPORTS TO THE COMMISSION o
Draft Sunnlement No.
2 to Generic Letter 88-20,
" Accident Management Strateales for Consideration in the Individual Plant Examination Process" (Report to Chairman Carr dated-November 20,.1989)-
o Pronosed Resolution of Generic-Issue' 87.
"HPCI Steam Line Brgik with2ut Isolation" (Report - to Chairman Carr, dated =
November 20, 1989)
\\
o Coherence in the Reaulatory Process (Report to chairman carr, l
dated November 24, 1989)-
j o
Examnle of MRC Rmnloyees-Inventinc or-Innosina New Requirements (Letter -to Chairman Carr, dated November 20, d
1989) l i
LETTERS TO THE ACTING _EQQ o
Eglationshin of the Ouantitative safety Goal to-the Concent.
of Adeaunte Protection (Letter to J. -Taylor, Acting EDO, dated November-20, 1989)-
i o
Module 1 of the Draft Safety Evaluation Renort for the l
Advanced Boilina Water -Reactor Damian - (Letter to J. Taylor, Acting EDO, dated Noven'ber 24, 1989)
OTHER~ ACTIONS, AGREEMENTS. ASSIGNMENTS. AND REQUESTS Nine Mile Point Unit 1 Restart (Memorandum from R. Fraley for o
J. Taylor, dated November 24, 1989)
The Committee decided to continue its review of.the restart l
of'Nine Mile Point Unit 1 subsequent to the staff's approval-j of-the restart.
Since the Committee's review may.take place
?
during the startup phase, the Committee decided that there is no need to delay the restart of_this plant.
-(See' memorandum from R. Fraley for J. Taylor, dated November 24, 1989.)
)
nrn
1 AAAR - 355th ACRS Meeting 2.
t o-Proocsed 10 CFR Part 55. Operators' Licensees-g The-Committee-decided to review the proposed revision-of 10 CFR Part 55 to require compliance with fitness for duty i
programs and conforming. modifications to the commission's.
(Memorandum from-R. Fraley for J.
Roe dated November 24, 1989) o NUMARC/NUPMX License Renewal Tonical Reports The Committee decided - that the ' ACRS should- ' be _ given an opportunity to review and comment on the industry topical reports related to license renewal that are being prepared by NUMARC-and/or being submitted to the NRC' staff for review.
The.NRC staff has been requested _to-provide > copies of.these:
reports to the ACRS and their evaluation 7of these reports when-available.
(See memorandum from R.
Fraley for T. - Murley, dated December 5, 1989.)
o
-ACRS/ACNW Resoonsibilities-The committee acknowledged the division ofLresponsibilities between the ACRS and-the'ACNW specified by the Commission in the memorandum from chairman CarrLdated November 6, 1989, and discussed mechanisms _to provide for joint input _in areas of mutual interest.
o Standardized Advanced LWRs The NRC staff briefed the Committee regarding the-status of its review of the following evolutionary and' advanced light water reactor designs:
Westinghouse SP/90 I
Westinghouse AP'600 Combustion Engineering System 80+
The. tentative schedule' proposed by the staff for the ACRS full.
Committee discussion of these designs is given below:
Westinghouse SP/90'(PDA)_ - April 1990 Westinghouse AP 600_
- April =1990 (Initial discussion)
Combustion Engineering System 80+ - February 1990 (Licensing Review Basis Document)
AAAR - 355th ACRS' Meeting 3
I o
Three Mile Island Nuclear Station Unit 2 The NRC staff - briefed -the - Committee regardina the status of:
- [
the recovery _ efforts, including the. investigation of the reactor vessel--lower head indications at TMI-2.
I o-
-ACRS Meetina Dates ~for Calendar Year 1990 The Committee approved 'the following meeting dates for=
calendar year 1990:
}
357th Meeting _
January 11-13, 1990 358th Meeting-February 8-10, 1990 359thl Meeting-March.8-10, 1990-360th-Meeting April 5-7,.1990-361st Meeting May 10-12, 1990 l.
362nd Meeting June l7-9, 1990
)
'363rd Meeting July 12-14,.1990 364th Meeting August 9-11, 1990.
?
365th Meeting
' September'6-8, 1990 366th~ Meeting October 4-6, 1990 367th; Meeting-November 8-10, 1990-i, 368th Meeting.
-December 6-8, 1990 (The June :1990 meeting ' dates may change' to accommodate the Second International Conference'of Advisory Committees.)
o Meetina with the Commission The Committee proposed a meeting:with the' Commissioners during the 356th ACRS. meeting, December' 14-15, 1989.
-Items
?
tentatively scheduled for discussion ares.
Status of ACRS activities related to:the development of containment design criteria for future plants.
NRC Safety Research Program budget--(Tentative)
" Management" of Licensee activities by NRC Regional-
. staff.
j (This meeting has been deferred'to January 1990.)
.,r
SUMMARY
/ LIST-OF FOLLOW-UP MATTERS o
The Committee suggested that Mr. Frank Gillespie, NRR, be invited -~to brief the Committee during the December 1989 meeting regarding the use of SALP ratings in the regulatory 4
I
j l?
l=
AAAR
-355th ACRS Meeting 4
o j'
f-
. process.-
(Mr. Fraley and.Mr. - Boehnert have the follow-up-action on-this matter.)
o The Committee suggested that the. Acting' EDO be invited to discuss coherence in the NRC. regulatory process, during the P
December
'1989:
ACRS meeting.-
..(Mr.
.Fraley and - Mr.
Quittschreiber have the follow-up action on'this matter.).
L<
o The Committee. hasL decidedt to. continue the L review of the j
restart of Nine Mile Point Unit.1 subsequent.to'the staff's approval of the restart.
(Mr. ~ Alderman. has the follow-up L
action on'this matter.)
o-The Committee has decided'to review proposed revisions 1to 10 L
CFR Part 55-to require compliance with fitness-for-duty programs - and' conforming modifications ~ to the Commission's L
(Mr. Alderman.has-the follow-up action on this matter.).
J o
The Committee agreed Lwith. the Thermal-Hydraulic Phenomena subcommittee's proposal: to hold. additional caseting(s)- to discuss further the adequacy?of the thermal-hydraulic loading definitions.for the ABWR" containment <and also the capability-of the thermal-hydraulic codes to model-BWR : core power stability.
(Mr. Boehnert has'the~ follow-upLaction.on this-matter.)
a o
The Committee decided ' that the ' ACRS., should be given an opportunity to review :and coraent. on ' the industry topical reports'related to license renewal'that are being prepared by NUMARC.
The NRC staff should provide. copies of these reports 1
I andJtheir-evaluation of theseereports to the ACRS.:
Itzwas proposed that the procedures ein tte: MOU between the: ACRS and l
the EDO ~ be used as the basis i'or these ' reviews..
(Mr.
l Quittschreiber has the-follow-up action on this matter.)
I-The Committee proposed 'to meet with the Commission during-the o
356th ! Teting,; December 14-15,.1989. = Items tentatively sched-uled~for discussion are:
Status of ACRS activities related to the development of
[
containment design' criteria:for. future plants..
NRC Safety Research Program budget (Tentative)
" Management".of Licensee. activities by NRC Regional staff.
'1 I
.-...a..
y s
AAAR=- 355th ACRS-Meeting.
5 i
o During the discussion'of-the Standardized Advanced LWRs, Dr.
Shewmon asked whether the fluence level in the core region for, CE System 80+ design is different from.that:for CE-System 80-design.
The staff stated that they would provide this_
information later.
(Mr. El-Zettawy has the follow-up' action; on.this matter.)
s o
.During-theidiscussion of Module 1 of-the.GE ABWR design, the following: requests for information were,made by several
' members of the Committee (Mr.. Alderman has the. follow-up action on these matters):.
Dr.-Shewmon' asked about the sulfur content for the-core' barrel for the GE ABWR.
Mr. Dillman, GE, said-he would send a specification that indicates sulfur.
j content.
?
Dr. Shewmon asked about.the cobalt content.-in-the stainless steel that is exposed to primary. coolant.
Mr. Dillman said he would provide this1information--
1 later.
Mr. Carroll-asked,' in.the case of.an,ATWSLevent, how long :it would take for the reactor.,to go i
subcritical.
Mr. Sawyer, GE, said he t would: provide j
this information-later.-
Dr.
Shewmon asked about the specifications for-chemistry controls of. low alloy steel used'in the Fine Motion Control Rod = Drive System. lMr.3Dillman y
said he would provide this infornation-later.
t Mr. Carroll asked._ how they. plan' to imeasure high.
fission product radiation.
- Mr. Dillmano said he would provide the details.-
l 1
l.
Mr. Michelso:) questioned whether or not the reactor l i.
pressure ves sel would ever have to be annealed.
Mr.-
Scalletti, NRR,.said that he would check and provide?
the information.later.
Mr. Michelso.) asked if GE had looked at the maximum 1
energy deposation in the reactor internal-pump area.
~
t from a fault that was uncleared, and whether i.t-would - cause enough pressure = to rupture the pump, housing.- Mr. Sawyer said the analysis had been done -
and it would be documented.
He said he would confirm this.
- ,.....~3
1 ji AAAR - 355th ACRS Meeting-6' i'
Mr. Michelson asked-if a specific station blackout l~
evaluation-- had beenL prepared for the ABWR.
Mr.
~ Sawyer said he would provide this information later.
Dr.;Catton: asked about'the probability offblowout~
lfor the reactor internal pump. Mr. Sawyer. said that i-
-he would' provide that number later.
i Mr. Michelson pointed out.that the time limit for RCIC operation. listed,as 30 minutes in the GE SSAR-3 is difforent'from that in the-staff's DSER.
Mr. -
j Scalletti;said theyiwill change the_DSER to reflect'
-recent'GE! amendments.
Dr.~ Catton asked how much energy is required ~ to heat the suppression poolLto 207 degrees.
Mr; Sawyern stated that he would provide this information later.
n Dr.
Catton asked whether GE had ' evaluated' the consequences of-extensive' scattering of insulation during a 'large pipe break. -
He askedh the' staf f -
whether they' have.. looked into this issue.
Mr.
r s
l Dillman, ? GE, and - Mr. t Parczewski,E NRR, i said they would lookLinto this.
Mr. Michelson asked - about L the reliability of: the-j' inflatable seals under accident! conditions.
Mr.
.Dillman said he would provide this information t
- later, 7.
FUTURE ACTIVITIES-The Committee agreed ' to the ' tentative scheduleL for, the December 14-15,-1989 ACRS' meeting as shown in Appendix-A.
= ~
i-APPENDIX A L
ITEMS TENTATIVELY SCHEDULED FOR THE 356TH ACRS MEETING, c
DECEMBER 14-16, 1989 Nuclear Power Plant Access Authorization - Review'and report on proposed final rule on Personnel Access Authorization Requirements for Nuclear Power Plants (10 CFR Part'73.56).
Containment Performance Improvement Program < - Review and report on d
. proposed NRC program to improve containment performancef uring severe accident conditions for all containment types except Mark I: containment; i
n
. Technical Training and Qualification Program for NRC Employees -
Briefing by NRC s",aff representatives regarding-training courses at the NRC. Technical Training Center at Chattanooga, TN.c J
7 Fitness for Duty - Review and report on proposed revision:of 10 CFR Part 55 to require operator compliance with NRC fitness-for-duty-programs and: conforming modification to the Commission's.
Meeting with Acting EDO - Discussion regarding ' lack' of.coherencelin the p
NRC regulatory process.
ACRS' Subcommittee Activities (0 pen) - Hear and discuss repor'ts of ACRS Subcommittees regarding-the status of assigned activities.regarding-l-
safety-related matters, including-the activities related to thermal-hydraulic phenomena, etc.
l-
- Evaluation of Operational Data (0 pen)
Briefing and discussion i
regarding use of. SALP ratings in the regulatory ; process.and elsewhere.
Meeting with the Commissioners (0 pen) -. Discussion of the following-items:
q Status of ACRS' activities related to the development of containment-design criteria for future plants l
1 l
NRC1 Safety Research Program budget Cientattve)
"Ma'agement" of Licensee activities-by NRC Regional staff.-
H n
(This meeting has been deferred to January 1990.)
9
+
?
l
-i
.