ML20202D340
| ML20202D340 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/20/1998 |
| From: | Imbro E NRC (Affiliation Not Assigned) |
| To: | Curry D AFFILIATION NOT ASSIGNED |
| References | |
| NUDOCS 9802170050 | |
| Download: ML20202D340 (5) | |
Text
-
hg iI f
f January 20, 1998
. Daniel Curry
-a Project Director !
? Persons Power Group Inc.
2675 Morgantown Road
- : Reading, PA 19607 1
Dear _ Mr ' Curryt
.On September 29,1997, you submitted for NRC review 'and approval the critical design characteristics (CDCs) for the accident mitigation systems for radiological events discussed in
~ Chapter 14 of the Millstone Unit 2 Final Safety Analysis Report (FSAR). The staff has completed its review of these critical characteristics.
The enclosure provides the results of the NRC's review of your submi+tal. In the enclosure, the NRC has ider.tified additional CDCs and interfacing systems that are important to the safety analyses described in Ch6pter 14 of the FSAR.l You are requested to inciude these CDCs and systems within the scope of your Independent Corrective Ar: tion Verification Frogram (ICAVP)
LTier 2 review of Millstone Unit 2. For the system paramete-
?ithin the scope of the Tier 2
.- review, you should verify that the values input to the analyses described in Chapter-14 of the i FSAR are consistent with those stated in Chapter 14 of the FSAR and the Technical -
-- Specifications, and are supported by the plant design data.
As described in the enclosure, the NRC identified several critical characteristics in your -
submittal that do not appear to require your Tier 2 review; To ensure adequate disclosure of :
your activities during the ICAVP Tier 2 review, you are requested to document the finalized set.
- of critical desis i characteristics in your ICAVP Tier 2 repost if you have any questions or comments, please contaci me at (301) 415-1490,
, LSincerely,' '.]L/MN k l
/ $ \\). -
s Eugene Imbro, Deputy Diredor
~ lCAVP Oversight.
Special Projc. Office Office of Nuclear Reactor Regulation
Enclosure:
-As stated cc w/ encl: See next page DISTRIBUTION.
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Northeast Nuclear Energy Company Millstone Nuclear Power Station Unit 2 -
cc:
Lillian M. Cuoco, Esquire Citizens Regulatory Commission Senior Nuclear Counsel ATTN: Ms. Susan Perry Luxton Northeast Utilities Service Company.
180 Great Neck Road
.l P. O. Box 270 -
Waterford, Connecticut 06385 Hartford, CT 06141-0270 Mr. F, C. Rothen Mr. Kevin T, A. McCarthy, Director
' Vice President - Work Services Monitoring and Radiation Division Northeast Utilities Service Company
- Department o' Environmental P.O. Box 128 Protection Waterford, CT 06385 79 Elm Street Hartford, CT 06106 5127 Charles Brinkman, Manager Washington Nuclear Operations Mr. Allan Johanson, Assistant Director ABB Combustion Engineering Office of Policy and Management 12300 Twinbrook Pkwy, Suite 330 Policy Development and Planning Rockville, MD 20852
' Division 450 Capitol Avenue - MS 52ERN Mr. D. M. Goebel P. O. Box 341441 Vice President - Nuclear Oversight
)
i Hartford, CT 06134-1441 Northeast Utilities Service Company P, O. Box 128
- Regional Administrator, Region I Waterford, CT 06385 i
U.S. Nuclear Regulatory Commission 475 Allendale Read Mr, M. L. Bowling, Jr.
King of Prussia, PA 19406 Pr.overy Officer - Millstone Unit 2 Wortheast Nuclear Energy Company First Seloctmen-P, O. Box 128 Town of Waterford Waterford, CT 06335 Hall of Records 200 Boston Post Road Senior Resident inspector Waterford. CT 06385 Millstone Nuclear Power Station clo U.S. Nuclear Regulatory Commission Deborah Katz, President P. O. Box 513 Citizens Awareness Network Niantic, CT 06357 P. O. Box 83
.Shelbume Falls, L1A G3170 Mr. David Amerine Vice President - Nuclear Mr. Wayne D. Lanning Engir,eering and Support Deputy Director of Inspections Northeast Utilities Service Company Special Projects Office P. O. Box 128 475 Allendale Road Waterford, CT 06385 King of Prussia, UA 19406-1415 Burlington Electric Department Mr. M. R. Scully, Executive Director clo Robert E. Fletcher, Esq.
y Connecticut Municipal Electric 271 South Union Street Energy Cooperative Burlington, VT 05402 30 Stott Avenue Ncrwich, CT 06360
Northeast Nuclear Energy Company Millstone Nuclear Power Station linit 2 cc:
- Mr. William D. Meinert Mr. John Buckingham Nuclear Engineer Department of Public U!i'.ty Control Massachusetts Municipal Wholesale Electric Unit Electric Company
-10 Liberty Square P. O. Box 426 New Britain, CT 06051 Ludlow, MA 01056 Mr. James S. Robinson Ernest C. Hadley, Esq.
Manager, Nuclear investmeats and 1040 B Main Street Administration P.O. Box 549 New England Power Company West Wareham, MA 02576 25 Research Drive Westborough, MA 01582 Joseph R. Egan, Esq.
i Egan & Associates, P.C.
Mr. B. D. Kenyon 2300 N Street, NW President and Chief Executive Officer -
Washington, D.C. 20037 Nuclear Group Northeast Utilities Se;vice Company The Honorable Terry Concannen P. O. Box 128 Co-Chair-Waterford, CT 06385 Nuclear Energy Advisory Council Room 4035 Mr. M. H. Brothers Legislative Office Building Vice President - Opetations Capitol Avenue Northeast Nuclear Energy Company Hartford, Connecticut 06106 P. O. Box 128 Waterford, CT 06385 Mr. Evan Woollacott Co-Chair Mr. John C. Markowicz Nuclear Energy Advisory Council Nuclear Energy Advisory Council 128 Terrys Plain Road 9 Susan Terrace Simsbury, CT 06070 Waterford, CT 06385-3515 Ms. P. l.oftus Mr. Don Schopfer Diractor - Regulatory Vice President and ICAVP Manager Northeast Nuclear Energy Company Sargent & Lundy P. O. Box 128 55 E. Monroe Street Waterford, CT 06385 Chicago,IL 60603 Mr. J. A. Price Unit Director - Millstone Unit 2 Northeast Nuclear Energy Company P. O. Box 128 Waterford, CT 06385
4.
ADDITIONAL SYSTEM PARAMETERS IMPORTANT TO SAFETY AMALYSIS FOR MILLSTONE UNIT 2 A.
SECTION 2.2," FUEL HANDLING ACCIDENT IN THE SPENT FUEL POOL"
- 1. Additional Mitigation Systems a.
Reactor Building Closed Cooling Water (RBCCW) System (shown on SDB M2-T2SDB-SFPC1 R0, but not included in Section 2.2.3, System Interface).
b.
Main Exhaust system for initial ventilation (shown on M2-T2SBD-ME1, but not included in Section 2.2.3, System interface).
- 2. Additional comments on Section 2.2.5.2 of the Critical Design Characteristics (CDC) a.
The Functional / System CDC: "Radi& tion monitoring system alarm setpoints include Fuel Handling Accident as a basis" is redundant with the other radiation monitoring CDCs in this section and should be deleted.
b.
The CDC: " Fuel pool designed without protruding structures that could damage fuel if dropped," should be de'eted. The licensee determined by analysis (FSAR Section 14.7.4.2) that if the Spent Fuel Pool (SFP) had a protrusion of indeterminate shape (assumed to be a line load), and a fuei assembly were accidently dropped and struck the protrusion causing the maximum amount of dexage to the fuet assembly, that the resulting radiological consequences would not exceed the limitations of 10 CFR Part 100.
c.
The reference for the Auxiliary Exhaust System (AES) in the third CDC should be FSAR 14.7.4.1.
d.
The Functional / System CDC' "SFP area air is aligned to exhaust through the EBFS
[ Enclosure Building Filtration System] prior to release thrrah the Unit 1 stack," should read; "SFP area air is aligned to exhaust from the AES through the EBFS prior to release through the Unit 1 stack."
B: SECTION 2.3," FUEL HANDLING ACCIDENT IN THE CONTAINMENT"
- 1. Additional comments on Section 2.3.5.2 of the Critical Design Characteristics a.
In Section 2.3.5.2, " Containment integrity and Radiation Control CSF [ Critical Safety Functions)," the last CDC should be consistent with Section 2.2. Modify the last CDC to read: "The radiation monitoring system monitors ventilation exhaust from the containment and auxiliary buildings and alarms upon indication of a fuel handling accident."
C: SECTION 2.4," SPENT FUEL CASK DROP ACCIDENTS"
- 1. Additional Critical Design Characteristics a.
Section 2.4.5.1, Functional / System CDC: "The SFP area air is aligned to exhaust from the AES through the EBFS prior to release through the Unit 1 stack."
~
Section 2.4.5.1, Functional / System CDC: "The radiation monit eing system alarms on a loss of shielding due to low water level in the fuel pool."
c.
Gection 2.4.5.1, Functional / System CDC: "The radiation monitoring system monitors the ventilation exhaust air from containment and auxiliary buildings and alarms on indication of a brach of fuel."
- 2. Additional comments on Section 2.3.5.2 of the Critical Design Characteristics a.
The CDC, " Containment Integrity and Radiation Control CSF," should read: "Fual fission product decay time at least one year." FSAR Section 14.7.5 is currently l
inconsistent with the requirements of Millstone Unit 2 Technical Specification (TS) l 3.9.16.1. This TS was changed to require a minimum one year of decay time.
D: Section 2.5," Hydrogen Accumulation in Containment"
- 1. Additional Mitigation Systems a.
Combustible Gas Control System does not appear to be included as an interfacing system required to mitigate the consequences of the accident. Section 6.2.5 of the NRC's Standard Review Plan (SRP) states that combustible gas control systems should include instrumentation needed to monitor system or component performance under norm'al and accident conditions. The instrumentation should be capable of determining that a system is performing its intended function, or that a system train or component is malfunctioning and should be isolated. The instrumentation should have readout and alarm in the control room. The containment hydrogen monitor shall meet the requirements of item II.F.1 of NUREG-0737 and NUREG-07.18, and the A.ppendix of Regulatory Guioe 1.97.
- 2. Additional Comments on Section 2.5 of the CDCs a.
CDCs for hydrogen generated by the radiolytic decomposition of organic materials exposed to containment spray solutions are provided. Parsons should verify the inventories and assumptions given in Section 2.5.5.1.
E: Section 2.6," Radiological Consequences of the Design Basis Accident"
- 1. Additional Comments on Section 2.6 of the CDCs.
a.
The primary containment leakage rate for the LOCA dose analysis should be based on the containment leakage testing described in Chapter 6 of the FSAR. Therefore, the containment leakage testing section of Chapter 6 of the FSAR should be referenced.
It should be noted that NUREGICR-5640 lists the containment leak rate as 3.0%
vol/ day for Millstone 2 instead of the reactor building rate cf < 0.5%/ day given as the CDC. The containment leak rate should be confirmed witn the onc given in Chapter 6 of the FSAR.
2
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