ML20077A276
| ML20077A276 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 11/15/1994 |
| From: | Richard Anderson NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-GTECI-A-47, REF-GTECI-SC, TASK-A-47, TASK-OR GL-89-19, TAC-M74965, NUDOCS 9411220241 | |
| Download: ML20077A276 (4) | |
Text
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Mi Northem States Power Company 414 Nicollet Mall Minneapolis, Minnesota 55401-1927 Telephone (612) 330-5500 l
November 15,1994 NRC Gen Ltr 89-19 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Supplemental Information Concerning Generic Letter 89-19 and USl A-47, " Safety implications of Control Systems in LWR Nuclear Power Plants" (TAC No. M74965)
References:
(1)
Generic Letter 89-19 dated September 20,1989 - Request for Action Related to Resolution of Unresolved Safety issue A-47 " Safety implications of Control Systems in LWR Nuclear Power Plants" (2)
NSP to NRC Letter dated May 4,1990 - Response to Generic Letter 89-19, Safety implications of Control Systems in LWR Nuclear Power Plants (3)
NSP License Amendment Request dtted October 21,1991 - Reactor Feedwater Pump Trip Instrumentation (4)
NSP to NRC Letter dated September 21,1992 - Withdrawal of Previously Submitted License Amendment Request Concerning Reactor Feedwater Pump Trip Instrumentation.
(5)
NRC to NSP Letter dated October 21,1992 - Monticello - Withdrawal of an Amendment Request (TAC No. M74965)
The purpose of this letter is to provide additionalinformation to the NRC staff concerning Generic Letter 89-19 (Reference 1). Generic Letter 89-19 addressed concems over the adequacy of reactor vessel overfill protection instrumentation in light water reactors. For BWRs, the instrumentation of concem would cause a trip of the reactor feedwater pumps on vessel high water level conditions. Generic Letter 89-19 also described the NRC Staff recommendations relative to the design, testing, and controls (including Technical Specifications) that should be applied to the reactor overfill instrumentation.
Reference (2) provided NSP'uesppgsp to GL 89-19. In that response, NSP reported that the Monticello reactor feedwater pumpinpJrd trumentation satisfied GL 89-19 except that the s
i0 9411220241 941115 PDR ADOCK 05000263 P
USNRC NORTHERN STATES POWER COMPANY October 21,1994 Page 2 instrumentation was not included in the plant Technical Specifications. NSP agreed to revise the Monticello Technical Specifications to include the changet recommended by Generic Letter 89-19 and submitted a license amendment request (Reference (3)) to accomplish this.
The NRC Staff subsequently contacted NSP and stated that, based on further review, the Staff no longer considered it necessary for the reactor feedwater pump overfill trip instrumentation to be included in the Monticello Technical Specifications. As a result of this discussion, NSP withdrew the associated license amendment request via Reference (4). The NRC Staff acknowledged this withdrawal and reaffirmed the NRC's position conceming Monticello in Reference (5).
In order to facilitate final closecut of this issue for Monticello, the NRC Staff (Beth Wetzel) recently requested that NSP provide confirmation that the reactor feedwater pump overfill trip instrumentation is not credited as the primary instrument protecting the fuel for any design basis accident or abnormal operational transient analysis described in the Monticello Updated Safety Analysis Report (USAR).
We have reviewed the Monticello USAR and confirmed that the reactor feedwater pump overfill trip instrumentation is not credited as the primary instrument protecting the fuel for any design basis accident or abnormal operational transient analysis described therein. Although the reactor feedwater pump high water level trip is discussed in USAR Section 14.4
("Feedwater Controller Failure - Maximum Demand" transient analysis), it is clarified elsewhere in the USAR (Section 11.8.2.3) and in supporting documentation that the purpose of the trip is to preclude the possibility of damage to the steam lines, turbine and related equipment due to water impingement and that the trip is not necessary for fuel protection.
This letter contains no new NRC commitments.
Please contact Terry Coss, Sr. Licensing Engineer, at (612) 295-1449 if you require any additional information conceming this submittal.
/
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Roger O. Anderson Director Licensing and Management issues cc: Regional Administrator-Ill, NRC NRR Project Manager, NRC Resident inspector, NRC State of Minnesota, Attn: Kris Sanda J. Silberg l
l
i TRANSMITTAL MANIFEST NORTHERN STATES POWER COMPANY NUCLEAR LICENSING DEPARTMENT MONTICELLO NUCLEAR GENERATI' G PLANT N
Supo!ementalinformation concemina ceneric letter 89-19 and USl A-47. " Safety inplications of control systems in LWR nuclear power plants"(TAC No. M74965)
Manifest Date: November 16,1994
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Monticello Intemal Site Distribution:
- Monti Document Control File NL Monti Plant File W J Hill, Plant MGR Steve Engelke Lyle Kamppinen Kaleen Hilsinhoff...
USAR File..
....Yes_X_ No Steve Ludders...
..NRC Commitment...Yes No_X_
Lila imholt.....
.Monti OC Sec
...Yes_X_ No
- 10, No dist to OC members above Mel Opstad...
.Monti SAC Sec..
...Yes_X_ No
-6
- Mail Room.
.Monti Posting.
..Yes No_X_ 7 NSP Internal Distribution (Ren Square,8th Floor)
E L Watzl, VP Nuc Gen R O Anderson, Dir LMI, SAC J K Gilchrist, LMI Communication Dept Yes No X
~ External NSP Distribution
- Doc Controf Desk,"NRCa Kris Sanda, State of Minn Regional Admin-lli,NRC Beth Wetzel, NRR-PM, NRC Steve Ray, SR Res insp, NRC
- Advance Distribution made by Site Licensing Correspondence Date : November 15,1994 i
J i
NRC Correspondence Manifest Instructions Document: tS>pplemedu / M ru % Pe: GL 5"!-l9 (USr A-47)
Manifest:
MO Advance Dist.
Additional Dist:
Delete Dist:
b e. Es q ed h e.
V lAt Um ppinen II Special Manifest Requirments /
USAR Yes No (Send copy to Kaleen Hilsenhoff)
NRC Commitment Yes No t/, (Send copy to Steve Ludders)
Resp Reminder Yes No 1/
Resis;Stdrt Date?
(Res'p Period LResp;Due!Date Action ~-
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s pt
?Lic'Contscti
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' ^
Res Start Date Resp Period Re M Contact Action:
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[MsplDus Date" Re'sp Start Date!
+ Resp Pe '
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LLic; Contact N Resp Start Date /
Resp Period Resp Due Date Action:
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Lic
Contact:
Monti OC Sec Yes /
No (10 copies to L Imholt, withhold distribution to OC ID addressees)
Monti SAC Sec Yes /
No (1 copy to SAC Sec File,4 Copies to non-NSP
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SAC members in weekly mailing)
Monti Posting Yes No (7 advance dist copies to J McNabb)
Ext comm Dept Yes No NSP H \\WORDVARCCORRWAN FORM DOC