ML20062M238
| ML20062M238 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/28/1993 |
| From: | Terry C NIAGARA MOHAWK POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NMP2L-1459, NUDOCS 9401060346 | |
| Download: ML20062M238 (6) | |
Text
i M Y NIAGARA l
.1%uMOHAWK NIAGARA MOHAWK POWER CORPORATION '301 PLAINFIELD ROAD, SYRACUSE,ItY.13212/ TELEPHONE (315) 474-1511 December 28,1993 NMP2L 1459 l
U. S. Nuclear Regulatory Commission ATI'N: Dwument Control Desk Washington, D.C. 20555 Re:
Nine Mile Point Unit 2 l
Docket No. 50-410 l
NPF-69 l
l Gentlemen:
SUBJECT:
Setpoint Methodology The Nuclear Regulatory Commission Staffissued Supplement 2 to the Safety Evaluation l
Report for Nine Mile Point Nuclear Station Unit 2 in November 1985. In Section 7.2.2.3 of Supplement 2, " Instrument Setpoints," the Staff approved the interim use of the Nine Mile Point Unit 2 setpoint muhodology, pending Staff resolution of the information presented by the Instrument Setpoint Methodology Group. On behalf of the Instrument Setpoint Methodology Group, General Electric Company (GE) submitted GE Topical Report NEDC-31336, " General Electric Instrument Setpoint Methodology," dated October 1986 to the Staff for review. NEDC-31336 is a detailed technical report which documents the basis and the methodology for establishing protection system trip setpoints and allowable values.
By letter dated October 6,1989, Niagara Mohawk committed to provide the Staff a plant specific technical assessment of the setpoint methods used within six months of the Staff's approval of NEDC-31336. The assessment would include the values assigned to each component of the combined channel error allowance, the basis for these values, and the methods used to sum the individual errors. On June 28,1993, Niagara Mohawk received notification that the Staff had completed its review and issued its safety evaluation of NEDC-
)
31336. The safety evaluation indicated that the gweral methods used by General Electric in selecting instrument setpoints were acceptable. However, as a resuli of the Staff's review, several issues were raised. General Electric's letter to the Staff dated September 8,1993, provided GE's response to these issues.
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U. S. Nuclear Regulatory Commission Page 2 The purpose of this letter is to provide to the Staff the results of Nine Mile Point Unit 2's plant specific technical assessment for instruments assumed to operate in Updated Safety Analysis Report Chapters 6 and 15 and for which the Instrument Setpoint Methodology Group calculations have been developed. The values assigned to each component of the combined channel error allowance and additional supporting information are contained in the relevant setpoint calculations and are available for your review. The assessment is based on GE NEDC-31336 and the clarifications provided in GE's letter dated September 8,1993.
The results of the assessment are summarized in the attached table. As indicated on the attached table, the existing Nine Mile Point Unit 2 protection system setpoints are conservative or equal when compared to the setpoints calculated using the methods delineated in NEDC-31336 and as clarified in GE's September 8,1993 letter. Therefore, the existing Technical Specification setpoints ensure that the reactor core and reactor coolant system are prevented from exceeding the licensing safety limits for the transients and accidents analyzed.
Accordingly, no Technical Specification changes are required.
Very truly yours,
/
C. D. T rry Vice President Nuclear Engineering CDT/JMT/ksj Attachment 0045860 0 pc:
Mr. T. T. Martin, Regional Administrator, Region I Mr. R. A. Capra, Director, Project Directorate, I-1, NRR l
Mr. J. E. Menning, Project Manager, NRR Mr. B. S. Norris, Senior Resident Inspector Records Management
NEDC-31336 CE EETPOINT NETHODOLOGY REOULTD FOR NMP2 Paga 1 of 4 f
TRIF FUNCTION CAlrULATED CURRENT SYTPOINT ANALYTIC ALLOWABLE NOMINAL ANALYTIC ALLOWABLE NOMINAL VALIDATED TECH SPEC LIMIT VALUE SETPOINT LIMTT VALUE SETPOINT r
SECTION AL AV NTSP AL AV Nf3P REACTOR PROTFITION SYSTEM l'escoor Vessel Seeem T2.2.1 13 1071reig
$106treig fl054poig 1071 peig fl057peig
$1037psig YES Dome Pressure High Reactor Vessel Water Level tenr (L3)RPS, T2.2.1-13 154.3 2 156.1 2 157.0 1543 2157.8 in a l59.3 in YES RHR T3 3.2-2.1.e 3 AD5 T3.3 3-2.A.2.c T3 3.3-2.B.2.c Reactor Vessel Water level High(LB) HPCS T3.3.3-2.C.I.c 222 3
$211.5 in s208.9 in 222.3 In
$2093 to
$202.3 in YES RCic T3 3.5-2.2 FW/TB T33.9-2.1.s.
207.7
$203.8 in 5203.1 in 207.0 in
$203.8 in
$2023 la YES Msiv closure T2.2.1-1.5 85% gen 187% cren 288% crea 855 gen 288% tyes 292% eyee YES
'Ibebene Stop Velve Clooste (also RFI)
T2.2.1 1.9 90% wen 291%cren 192% gen 90% open 293% open 2955 cree YES T3.3.4.2-2 I
Tertwne Control Velve Fest closure (also T2.2.1-l.10 400 pag 2410peig 2418pois 400peig 2465peig 2530peig YES RPT) '
T33.4.2-2.2
_.a.1 %
20 %
$18.5 %
S 17 %
YE5
'Dirtwns First Stage Pressere T3.3.1 1.9 20 %
$18.9%
(scram Bypeso)
T3.3.1-1.10 140 pois
$132.4 pois
$126.?reig 140pois
$129.6psig (1)
St19peig (I)
T33.4.2-1 Flow Bissed sinmissed T2.2.1-I.2.b
'aurniel Pe=er Upecele
- 1) Flow Bissed 0.58W + 65 %
10.58W+ 62%
50.58W+ 61 %
(2)
(3)
(4)
YES
- 2) High Flow Clenged 1I8.0% -
1 115.7 %
1 114.5 %'
(2)
(3)
(4)
YES r
APRM Fixed Flux Upscale T2.2.1-1.2.e 123 %
$120%
& l19 %
(2) s 120 %
5 118 %
YE5
NEDC-31335 C2 CETPOINT METHODOLOGY REIULTJ FOR NMP2 Pcgm 2 of 4
.w TRIP FUNCTION CALCULATED CURRENT SETPOINT ANALYT1C ALLOWABLE NOMINAL ANALYTIC ALLOWABLE NOMINAL VALIDATED TECH SPEC LIMIT VALUE SETPOINT LIMTT VALUE SETPOINT SECTION AL AV NTSP AL AV NTSP ISOLATION Main steam Line 1.cw Pressure T3.3.2-2.1.C.2 720 poig 2729 peig 2736 g sig 720 reig 2746psig 2766psig YES Main Steam line High Flow T3 3.2-2.t.C.3 112.9psid
$109.5psid 1108.2psid Ill.5psid
$109.5 paid
$103psid YES Condenser tow Vemm T33.2-2.1.e 7.0in Hg vec 273in 11g vec 27.4in Hg vec 7.0in Hg vec 27.6in Hg voc 2 8. Sin Hg vec YES ECCS Reactor Vessel Water level Lew (L2) (also isolation)
RCIC T33.5-2.1 88.8 in 295.9 in 298.5 in 88.8 in 2101.8 in 2108.8 in YFS HPCS T3 3.2-2.1.s.2 N54 T3 33-2.C.I.s RRCS T33.4.1-2.1 Reactor Vessel Water level low (LI)
(also isolation)
-2.2 in 24.9 in 27.5 in
-2.2 in 210.8 in 217.8 in YES N54 T3 3 3-2.A.I.e T3 3 3-2.A.2.s T3 33-2.B.I.e T333-2.B.2.s Drywell High twssure T2.2.1 1.7 2.0 psig
$1.92 psig
$1.88 psig 2.0 reig
$1.88 pois 11.68 psig YES T33.2-2.1.b T33.2-2.2.h T333-2.A.I.b T3.3.3-2.B. I.b T333-2.C.I.b LPCI Injection Velve Differential Low T3.3 3-2. A. I.e 173 paid f160 psid 1152 paid 173 psid 1850 psid(dec) 1130 paid (dec)
YE5 Pressure Permissive LPCS liiection Velve DitTerersial low T333-2.A.I d i11.4 psid 1101 psid 193 psid 1Il.4 paid 198 psid (dec) 188 psid (dec)
YES Pnssure Permissive a
m m
a
NEDC-31336 CE CETPOINT METHODOLOOY RESULT 3 l'OR NMP2 Page 3 of 4 TRIP FUNCTION CAIEULATED CURRENT SETTUINT ANALYTIC ALLOWABLE NOMINAL ANALYTIC ALLDWABLE NOMINAL VALIDATED TECH SPEC LIMTT VALUE SETpOINT LIMfT VALUE SITPOINT SECTION AL AV FRSP AL AV IGSP LPCI Pump Discharge High Pressure T3 3 3-2. A.2.e 100 psig 1103 psig 1806 psig 100 peig 1115 pois Gnc) 1125 pois Gnc)
YES Permissive LPCS Pump Discharge High Pressure TJ J J-2.A.2.d I10 psig Al14 psig 1117 psig i10 psig 1125 reig One) 1145 peig Gnc)
YES Permissive Condensate Storage Tank Low 12 vel T3.3 3-2.C. I.d 0.0 (7) 10.8 in 11.5 in X in 1 X + 2.5 in A X + 5 in YES HPCS 194.5 in 197 in (7)
Condensate Storage Tank I.mw Level T33.5-23 0.0 (7) 10.4 in
>0.7 in Y-0.6 in
> Y in AY +3 in YES TeCIC 1801 in 1102 in G)
C)
Autometic Depressurization Symem Timer T333-2.A.2.b 120SEC Sil7 SEC Sil5 SEC 120 SEC SI17 SEC
$105 SEC YE3 UTHER Rod Block Monitor (BWR4/5)
None
$0.66W+ 50%
S0.66W + 47%
10.66W+ 45 %
(2)
(5)
(6)
YES Reactor Vessel Steam Dome High T33.4.1 2.2 1080psig
$1076 psig 11069 pois 1080 psig
$1065 peig
$1050 pois YES Pressure (ATWS)
Safety Relief Valve Relief Pressure None i106.1116,1126 1 1098,1108,1118 1 1088,1098, (2)
(2) 5 1076,1086, YES ll36,Il46 psig Il28,ll38 psig 1108,1118,1128 1096,1106,1116 psig pois (8)
(1)
Calculation results are in
- percent of span
- for 0 700.5 pois ronge transmitters. Technical Specification requirements are in comsponding psig values.100% corresponds to turtiine valves wide open steam flow.
(2)
His value is nd available.
(3) 10.58 (W-AW)+62% with a maximum ofS115.5% of Rited nermal Power.
W = percent of rated recirculation drive flow which produces rated Core flow. AW=0 for two loop operation. AW-5% for single lony operation. Calculation results for inarumentation uncertainties are valid for AW=5 %. (Typical for notes (3)-(6)).
(4) 10.58(W-AW)+ 59% with a maximum of $113.5% of Rated Dermal Power.
(5) 10.66 (W-AW)+47% with a maximum of 113% (see Core Operating Limits Report).
(6) 10.66 (W-AW)+ 44% with a maximum of I10% (see Core Operating Umits Report).
(7)
Cumnt and calculated allowances for instrumerd uncertainties are with respect to a reference level, provided by the plant A/E. He reference level corresponds to the minimum coniensate storage tank level required for pung operation. De Technical Specification allowable values and setpoints include the reference level.
(8)
Values from Oeneral Electric Design Spec Data Sheets. Deze setpoints are not in Technical Specifications.
l Page 4 of 4 NEDC-31336 GE SETPOINT METHODOLOGY RESULTS FOR NMP2 DISCUSSION t.
Calculations for the instrument setpointo described in the NRC approved Licensing Topical Report (LTR) " General Electric Instrument Setpoints", MEDC 31336, October 1986 have been performed for Nine Mile Point 2.
The results are summarized in this table. The calculations were performed by CE using the methodologies described in the LTR and incorporating plant unique features such as instruments and environments. The following describes the details of the tables, i
Trip Function - The instruments listed are based on the items contained in the LTR modified to the Nine Mile Point 2 design.
Thus, the High Containment Pressure is not contained in the list since it is a BWR/6 design feature and is not included in BWR/5s.
In addition, the SRV Safety function is not described since the NRC in the SER dated February, 1993 removed the mechanical function from the scope of the IEC review. Credit for the relief function of the SRV's is not assumed in the KMP2 safety analysis. Therefore, there are no associated Technical Specifications for these functions.
(1)
Calculated AL - values used in the setpoint calculations (2)
Calculated AV - The values listed are based on the instrument setpoint methodology and account for the appropriate error terms in the calculation as described in the LTR (i.e. accuracy, calibration, process i
measurement accuracy, primary element accuracy and any applicable bias).
j The values are 95% probability single sided.
l (3)
Calculated NTSP - The values listed are based on the instrument setpoint methodology and account for the appropriate error terms in the calculation as described in the LTR (i.e. accuracy, calibration, process measurement accuracy, primary element accuracy, drift and any applicable i
bias). The values are 95% probability single sided and are adjusted, if l
necessary, to ensure 90% licensing event report avoidance and 95%
l spurious trip avoidance.
(4)
Current AL - values obtained from GE Design Spec Data Sheets.
(5)
Current AV - The values listed are contained in the current Nine Mile Point 2 Technical Specification Allowable Values (AV).
(6)
Current NTSP - The values listed are contained in the current Nine Mile Point i Technical Specification Nominal Trip Setpoints (NTSP).
(7)
Validated - a "yes" confirms that the current Technical Specification Allowable Value and Nominal Satpoint are validated by the calculation and no Technical Specification change is required.
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