NUREG-1342, Discusses New multi-plant Action MPA F-72, SPDS-Response to Generic Ltr 89-06, Initiated to Accurately Reflect Status of SPDS Issue in Sims.Procedures Should Be Followed by Affected Plants as Indicated
| ML20247D228 | |
| Person / Time | |
|---|---|
| Issue date: | 07/17/1989 |
| From: | Hall J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-1342, RTR-NUREG-737, TASK-1.D.2, TASK-TM GL-89-06, GL-89-6, TAC-73630, TAC-73631, TAC-73632, TAC-73633, TAC-73634, TAC-73635, TAC-73636, TAC-73637, TAC-73638, TAC-73639, TAC-73640, TAC-M73626, TAC-M73627, TAC-M73628, TAC-M73629, NUDOCS 8907250099 | |
| Download: ML20247D228 (4) | |
Text
- - _ _ -
1 July 17, 1989 l
MEMORANDUM FOR:
All NRR Project Managers Distribution l
, Docket f.1_ les RHall FROM:
James R. Hall, Project Manager NRC & Local PDRs OGC Project Directorate III-3 PDIII-3 r/f EJordan Division of Reactor Projects - III,MVirgilio BGrimes IV, Y and Special Projects JHannon ACRS(10)
PKreutzer Gray File
SUBJECT:
MPA F-72: SAFETY PARAMETER DISPLAY SYSTEM -
REckenrode RESPONSE TO GENERIC LETTER 89-06 RDudley JThoma Generic Letter (GL) 89-06, " Task Action Plan Item I.D.2 - Safety Paraneter Display System," issued April 12, 1989, requires all licensees of operating plants, applicants for operating licenses and holders of construction permits (except those listed in Enclosure 1) to provide information to enable the NRC staff to determine the implementation tatus of each plant's Safety Parameter i
Display System (SPDS). NUREG-1342, an enclosure to GL 89-06, describes the l
NRC staff's experience in reviewing SPDS's and provides examples of design j
features found acceptable and unacceptable by the staff. This additional l
guidance was provided to licensees to clarify the requirements contained in i
NUREG-0737, Supplement 1, dated December 17, 1982.
Generic Letter 89-06 is intended to expedite closure of the SPDS issue by requiring all respondents to:
1 I
(1) certify that their SPDS currently meets all huREG-0737, Supplement 1 requirements, or (2) certify that their SPDS will be modified to fully meet the requirements in accordance with a specified implementation schedule, or (3) provide a detailed discussion justifying the acceptability of any differences
)
between their SPDS design and the staff's acceptance criteria. The Human Factors Assessment Branch (HFAB) will review licensee responses to GL 89-06.
HFAB will prepare sample letters, individual letters or safety evaluations, as j
appropriate, for transmittal to all licensees.
)
l In order to accur6tely reflect the status of the SPDS issue in the NRC Safety i
Issues Management System (SIMS), a new multiplant action (MPA) has been
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inititted, MPA F-72, " Safety Parameter Display System - Response to Generic Letter 89-06."
This new MPA will apply to all plants required to respond to the geneiic letter, New Technical Assignment Control (TAC) numbers will be opened by the lead project manager (LPM) for the review of responses for the plants listed in Enclosure 2.
Consequently, all currently open TAC's for these plants under MPA F-09 will be closed as of the date of this memorandum (For l
SIMS purposes, this date will eppear in the Licensing Action Complete column; i
"N/A" will appear in the Implementation Corrplete column). MPA F-09 will remain open to track the status of SFDS for the 15 plants in Enclosure 1, however, since this issue is nearly complete for these plants, this MPA is expected to be closed within the next few months.
The following procedures should be followed in entering SIMS data for liPA F-72 via the Project Manager's Report (PMR):
(1) The date of the licensee's response to CL 89-06 should be enterei in the " APPL DATE" field, i
1
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8907250099 890717 h
PDR ORG NRRB
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PDC 1
All NRR Project Managers '(2) The date of the NRC letter to the licensee closing the issue should be entered in the (Licensing Action) " COMPLETION DATE" field.
(This is also the date that the assigned TAC number is closed).
(3) For " LICENSEE IMPLEMENT DATE", enter:
(a) The date of the NRC letter to the licensee closing the issue
-(followed by the suffix "c"), for those plants certifying that their SPDS currently meets NRC acceptance criteria or for those plants for which the staff approves an existing alternate design, or (b) The date that all SPDS modifications necessary to meet NRC acceptance criteria will be completed, as approved by NRC letter.
(Licensees should provide written confirmation following completion of modification and PM's should indicate "c" on the PMR,) or (c) The date that all SPDS modifications will be completed, provided the staff has accepted the proposed alternative SPDS design had schedule in a letter or safety evaluation.
(Licensees should provide written confirmation following completion of modifications and PM's should indicate "c" on the PMR.)
For those licensees that certify under oath or affirmation that the SPDS design for their plant (s) meets or will meet the staff's acceptance criteria, verification vill not be required. NRR will perform or recommend verification
' apeci. fans for selected plants that deviate from the staff's SPDS acceptance criteric.
Any questions regarding the tracking of SPDS issues under MPA F-72 or MPA F-09 should be directed to the LPM, Randy Hall at X21391.
/s/
James R. Hall, Project Manager Project Directorate III-3 Division of Reactor Projects - III, IV, Y and Special Projects
Enclosures:
As stated
- see previous page for concurrence Office:
PM/PDIII-3 SC/HFAB TA/DRSP TA/DRP PD/PDIII-3 Surname:
RHall/mr*
REckenrode*
RDudley*
JThoma*
JHannor.*
Date:
07/06/89 7
07/07/89 07/06/89 07/10/89 07/07/89 Office:h(A)AD:DR 35 (A
SP Surname: MVirgilio: sam Gu>1ahan Date:
07/th/89 07/ p /89 L
1 -~ ]
"i
(,,
A t'
Plants Not Required to Respond to GL 89-06 Big Rock Point Catawba 1 & 2 Clinton Hatch 1 & 2 McGuire 1 & 2 Millstone 3
. River Bend Soutu Texas 2 Susquehanna 1 & 2 Vogtle 2 Yankee Rowe f.
/
Ii e
i MPA F-72: Safety Parameter Dis) lay System - Response to GL 89-06 New TAC Nurabers Opened by
.PM for the Following Plants:
TAC #
TAC #
TAC #
R73576 Arkansas 1 7T675 Millstone 1 Turkey Point 3 73713 7 Arkansas 2 6 Millstone 2 Turkey Point 4 7371V 8 Beaver Valley 1 7 Monticello Vermont Yankee 7372D 9 Beaver Valley 2 8 Nine Mile Point i Vogtle 1 1
73630 Bellefonte 1 9 Nine Mile Point 2 Waterford 3 2
1 Bellefonte 2 735BU North Anna 1 Watts Bar 1 3
2 Braidwood 1
-~'I North Anna 2 Watts Bar 2 4
3 Braidwood 2 2 Oconee 1 WNP 2 7
1 4 Browns Ferry 1 3 Oconee 2 Wolf Creek 6
l li Browns Ferry 2 4 Oconee 3 Zion 1 7
6 Browns Ferry 3 5 Oyster Creek 1 Zion 2 73728 7 Brunswick 1 73T97 Palisades 8 Brunswick 2 7T6H5 Palo Verde 1 l
9 Byron 1 7 Palo Verde 2 l
73640 Byron 2 8 Palc Verde 3 1 Callaway 9 Peach Bottom 2 2 Calvert Cliffs 1 7359U Peach Bottom 3 3 Calvert Cliffs 2 1 Perry'1 4 Comanche Peak 1 2 Pilgrim 5 Comanche Peak 2 3 Point Beach 1 73648 Cooper 4 Point Beach 2 73649 Crystal River 5 Prairie Island 1 736 W D. C. Cook 1 6 Prairie Island 2 73647 D. C. Cook 2 7 Quad Cities 1 716 W Davis-Besse 8 Quad Cities 2 1
Diablo Canyon 1 Y Rancho Seco 2
Diablo Canyon 2 7375U Robinson 3
Dresden 2 1 Salem 1 4
Dresden 3 2 Salem 2 5
Duane Arnold 3 San Onofre 1 5
Farley 1 4 San Onofre 2 7
Farley 2 5 San Onofre 3 8
Fermi 2 6 Seabrook 1 9
Fitzpatrick 7 Sequoyah 1 73660 Fort Calhoun 8 Sequoyah 2 1
Fort St. Vrain 9 Shoreham 2
Ginna 737TU South Texas 1 3
Grand Gulf 1 St. Lucie 1 4
Haddam Neck 2 St. Lucie 2 5
Harris 1 3 Summer 1 6
Hope Creek 1 4 Surry 1 7
Indian Point 2 5 Surry 2 B~
Indian Point 3 6 Three Mile Island 1 9
Kewaunee 7 Trojan 7T6 F LaSalle 1 1
LaSalle 2 2
Limerick 1 3
Limerick 2 4
Maine Yankee