ML17291A422
| ML17291A422 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 09/26/1994 |
| From: | WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML17291A421 | List: |
| References | |
| IEB-88-007, IEB-88-7, NUDOCS 9410040140 | |
| Download: ML17291A422 (27) | |
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REQUEST FOR AME NT TO TECHNICAL SPECI%< IONS TO INCREASE POWER LEVEL FROM 3323 MWt TO 3486 MWt, SUPPLEMENTARY INFORMATION Attachment 3 Page 1 of 17 TECHNICAL SPECIFICATION PAGES and BASES CHANGES Two power/flow maps are provided for Figures 3.2.6-1, 3.2.7-1, 3.2.8-1, and 3.4.1.1-1. The first map reflects the present Technical Specification power/flow map with the proposed changes superimposed for comparison and the second shows only the proposed power/flow map.
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POWER DISTRIBUTION LIMITS mmaOu~O C0VY 3/4. 2. 6
~ ~ POWER/FLOW INSTABILITY LIMITING CONDITION FOR OPERATION 3.2.6 Operation with THERMAL POWER/core flow conditions which lay in Region A of Figure 3.2.6-1 is prohibited.
ICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than f A THERMAL POWER and core flow is less than or equal to 45K of rated core flow.
ACTION:
With THERMAL POWER/core flow conditions which lay in Region A of Figure 3.2.6-1, then as soon as practical, but in all cases within 15 minutes, initiate a MANUAL SCRAM.
SURVEILLANCE RE UIREMENTS K
4.2,6 The THERMAL POWER/core flow conditions shall be verified to lay outside Region A of Figure 3.2.6-1 once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when operating in the region of APPLICABILITY.
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/Idaho jan) 1%c ~/Oup g,z. 0 "I-WASHINGTON NUCLEAR - UNIT 2 3/4 2-5 Amendment No. g4
70 Aeglan A 6Q K
50 A 0z
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c4 E
co 30 I- A I 0 U 20 lO 20 30 40 50 60 70 Core Flovr (% Bated}
operating Region Limits of Specification 3.2.6 Fi~ 3.2.6-4
t 80 Region A (45F, 62.8P) 60 e
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Woo y0 40 0 100% Rod Une C
E (23.8F, 35.3P)
I- 20 0
20 30 40 50 60 70 Core Flow (% Rated)
Operating Region Limits of Specmcation 3.2.6 Figure 3.2.6-5
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3/4.2 PONER DISTRIBUTION LIMÃ 3/4. 2. 7 STABILITY MONITORING " TWO LOOP OPERATION LIMITING CONDITION FOR OPERATION 3.2.7 The stability monitoring system shall be operable" and the decay ratio of the neutron signals shall be less than .75 when 'operating in the region of APPLICABILITY.
APPLICABILITY: OPERATIONAL CONDITION 1, with two recirculation loops in operation and THERMAL POWER/core flow conditions which lay in Region C of Figure 3.2.7-1.
ACTION: ~
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- a. With decay ratios of any two (2) neutron signals greater than .75 or with two (2) consecutive decay ratios on any single neutron signal greater than .75.
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As soot as practical, but in all cases within 15 minutes, initiate action to reduce the decay ratio by either decreasing THERMAL POWER with control rod insertion or increasing core flow with recirculation flow control valve manipulation. The starting or shifting of a recirculation pump for the purpose of decreasing decay ratio is specifically prohibited.
- b. With the stability monitoring system inoperable and when operating in the region of APPLICABILITY:
As soon as practical, but in all cases within 15 minutes, initiate action to exit the region of APPLICABILITY by either decreasing THERMAL POWER with control rod inser:ion or increasing core flow with recirculation flow control valve manipulation. The starting or shifting of a recirculation pump for the purpose of exiting the region of APPLICABILITY when the stability monitoring system is inoperable is specifically prohibited. Exit the region of APPLICABILITY within one (1) hour.
SURVEILLANCE RE UIREMENTS 4.2. 7. 1 The provisions of Specification 4.0.4 are not applicable.
- 4. 2. 7. 2 The stability monitoring system shall be demonstrated operable" within one (j) hour prior to entry into the region of APPLICABILITY.
4.2.7.3 Decay ratio and peak-to-peak noise values calculated by the stability monitoring system shall be monitored when operating in the region of APPLICABILITY.
"Verify that the stability monitoring system data acquisition and calculational modules are functioning, and that displayed values of signal decay ratio and peak-to-peak noise are being updated. Detector levels A and C (or B and D) of one LPRM string in each of the nine core regions (a total of 18 LPRM detectors) shall be monitored. A minimum of four (4) APRMs shall also be monitored.
WASHINGTON NUCLEAR - UNIT 2 3/4 2-7 Amendment No. 94
A, 70 Aegion A 60 K
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)g) l0 0
20 30 40 50 60 70 Core Flovr (% Bated)
Operating Aegion Limits of Specification 3.2.7 Figure 3.2.7-4
80 Region A (45F, 62.8P) 60 e
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Region C (45F, 50.3P)
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(23.8F, 30.3P)
I- (23.8F, 35.3P) 20 0
20 30 40 50 60 70 Core Flow (% Rated)
Operating Region Limits of Specification 3.2.7 Figure 3.2.7-1
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3/4.2.8 STABILITY MONITORING " SINGLE LOOP OPERATION LIMITING CONDITION FOR OPERATION 3.2.8 The stability monitoring system shall 'be operable" and the decay ratio of the neutron signals shall be less than .75 when operating in the region of APPLICABILITY.
APPLICABILITY: OPERATIONAL CONDITION 1, with one recirculation loop in operation and THERMAL POWER/core flow conditions which lay in Region C of Figure 3.2.8-1.
ACTION:
04 8, u.o l ~IR 4
- a. With decay ratios of any two (2) neutron signals greater than .75 or with two (2) consecutive decay ratios on any single neutron signal greater than .75:
O~ 4B~~ eg As soon-as practical, but in all cases within 15 minutes, initiate action to reduce the decay ratio by either decreasing THERMAL POWER with control rod insertion or increasing core flow with recirculation flow control valve manipulation. The starting or shifting of a recirculation pump for the purpose of decreasing decay ratio is specifically prohibited.
- b. With the stability monitoring system inoperable and when operating in the
~egion of APPLICABILITY:
As soon as practical, but in all cases within 15 minutes, initiate action to exit the region of APPLICABILITY by decreasing THERMAL POWER with control rod insertion. Exit the region of APPLICABILITY within one (1) hour.
SURVEILLANCE RE UIREMENTS 4.2.8.1 The provisions of Specification 4.0.4 are not applicable.
4.2.8.2 The stability monitoring system shall be demonstrated operable*
within one (1) hour prior to entry into the region of APPLICABILITY.
4.2.8.3 Decay ratio and peak-to-peak noise values calculated by the stability monitoring system shall be monitored when operating in the region of APPLICABILITY.
"Verify that the stability monitoring system data acquisition and calculational modules are functioning, and that displayed values of signal decay ratio and peak-to-peak noise are being updated. Detector levels A and C (or B and 0) of one LPRM string in each of the nine core regions (a total of 18 LPRM detectors) shall be monitored. A minimum of four (4) APRMs shall also be monitored.
WASHINGTON NUCLEAR - UNIT 2 3/4 2"9 Amendment No. 94
Iye go 70 Ilegion A 60
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K eglon 50 Cl' o 40 Z b Vo
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10 0
20 30 40 50 70 Core Flow (% Bated)
Operating Region Limits of Specification 3.2.8 Figure 3.2.8-1
T 80 Region A (45F, 62.8P) 60 e
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Region C C (45F, 50.3P) 0" Region B
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y0 40 0 400% Rod Une C5 E 80% Rod Une 0)
I (23.8F, 30.3P)
(23.8F, 35.3P) 20 0
20 30 40 50 60 70 Core Flow (% Rated)
Operating Region Limits of Specification 3.2.8 Figure 3.2.8-1
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80 Region A (45F, 62.8P) 60 Region C e
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500% Rod Line E 80% Rod Une 0)
(23.8F, 30.3P)
(23.8F, 35.3P) 20 0
20 30 40 50 60 70 Core Fiow (% Rated)
Operating Region Umits of SpecNcation 3.4.1.1 Figure 3.4,1,5-1
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POWER DISTRIBUTION LIMITS BASES slightly increasing the time required for the normal scram to suppress the flux.
3/4.2.4 LINEAR HEAT GENERATION RATE This specification assures that the Linear Heat Generation Rate (LHGR) in any rod is less than the design linear heat generation even densification is postulated.
if fuel pellet 3/4. 2. 6 prob combin POWER/FLOW MINIM ~ fh'M INSTABILITY ility of limit cycle neutron p~
flux oscillations exists depending tions of operating conditions (e.g., power shape, bundle powe n
, and bundle ow).
In Feb ary, 1984, GE issued SIL 380 addressing boiling i tability and supplying sev al recommendations. In this SIL, the power/f w map was divided into se ral regions of varying concern. It also scussed the objectives and ph> osophy of "detect and suppress," coin' the phrase.
The ANF topical ort for COTRAN (XN-NF-691P) scusses boiling insta-bility. The SER writte on this topical (dated Ma 0, 1984) interprets the topical to require that t detect-and-suppress rveillance be used in regions which have code calculated cay ratios .75 or reater and that operation is forbidden in regions having c culated decay atios of .9 and greater.
The NRC Generic Letter 86-02 ddres d both GE and ANF (then EXXON) stability calculation methodology a ated that due to uncertainties, General Design Criteria 10 and 12 could not met using analytic procedures on a BWR 5 design. The letter espoused GE 3 and stated that General Design Criteria 10 and 12 could be met imposi the SIL 380 recommendations in operating regions of potential nstability. The NRC concluded that regions of potential instability consti ed calculated cay ratios of .8 and greater by the GE methodology and .75 nd greater by the E ON methodology.
Predicated on the L 380 endorsement, WNP-2 h divided the power/flow map on the following oundary lines:
- l. 80K ro ine 2 45K c e flow line
- 3. 10 rod line
- 4. N ural Circulation flow line
- 5. inimum Forced Circulation for normal recirculation line is division conforms to the SIL 380 recommendations. For LCO 2.6, the re ' of concern (Region A) is bounded by the more conservative of'eit r the 10 X rodline or a line defining a calculated decay ratio of 0.9, the natu 1 circulation flow line, and the 45K core flow line. ,Calculated decay ratios mutate-Re~a-A-mus4-b h
WASHINGTON NUCLEAR - UNIT 2 B 3/4 2"5 Amendment No. 84
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42 P WER FLOW IN TABILITY At the high power/low flow corner of the operating domain, a small probability of limit cycle neutron flux-oscillations exists depending on combinations of operating conditions (e.g., power shape, bundle power, and bundle flow).
In 1984, GE issued SIL 380 addressing boiling instability and made several recommendations.
In this SIL, the power/flow map was divided into several regions of varying concern. It also discussed the objectives and philosophy of "detect and suppress." The SIL recommends that REGION A be bounded by the 100% rod line and REGION C be bounded by the 80% rod line.
The NRC Generic Letter 86-02 discussed both the GE and SIEMENS (then EXXON) stability methodology and stated that due to uncertainties, General Design Criteria 10 and 12 could not be met using available analytical procedures on a BWR. The letter discussed SIL 380 and stated that General Design Criteria 10 and 12 could be met by imposing SIL 380 recommendations in operating regions of potential instabilities. The NRC concluded that regions of potential instability constituted decay ratios of 0.8 and greater by the GE methodology and 0.75 by the SIEMENS methodology which existed at that time.
SIEMENS Power Corporation has recently developed an improved stability computer code STAIF. A topical report (EMF-CC-074P) which describes the STAIF stability code and provides benchmarking against reactor data was submitted to the NRC in 1993. The NRC issued a SER approving the STAIF stability code for establishing stability boundaries on April 14, 1994. In the SER on STAIF the NRC stated the uncertainty in the STAIF code was 20%.
The STAIF stability code has been used to establish the stability region boundaries for WNP-2.
The lower boundary of REGION A was defined to assure it bounds a decay ratio of 0.9.
REGION C was conservatively defined to bound a decay ratio of 0.75.
The stability REGIONS A and B are shown in Figure 3.2.6-1. REGION A conforms to the recommendations of SIL 380 in that REGION A bounds a calculated decay ratio of 0.9.
Operation in REGION A is prohibited. REGION C bounds a decay ratio of 0.75.
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r 3/4.2.7 STABILITY MONITORING - TWO LOOP OPERATION 53/4z +
At the high power/low flow corner of the operating domain, a small prob-abil'ity of limit cycle neutron flux oscillations exists depending on combina-tfons of operating conditions (e. g., rod patterns, power shape). To provide assurance that neutron flux limit cycle oscillations are detected and sup-pressed, APRM and LPRM neutron flux signa/ decay ratios should be monitored while operating in this region('R ~-. ~ Cg Stability tests at operating BWRs were reviewed to determine a generic region of the power/flow map in which surveillance of neutron flux noise levels should be performed. A conservative decay ratio of 0.75 was chosen as, the basis for determining the generic region for surveillance to account for the plant to plant variability of decay ratio with core and fuel designs. This generic region has been determined to correspond to a core flow of less than or equal to 45K of rated core flow and a thermal power cu<ic4 M c'CCc~ c. c
~~ C7i 7$ pc+7'cog Stability monitoring is performed utilizing the ANNA system. The system shall be used to monitor APRM and LPRM signal decay ratio and peak-to-peak noise values when operating in the region of concern. A minimum number of LPRM c and APRM signals are required to be monitored in order to assure that both global (in-phase) and regional (out-of-phase) oscillations are detectable.
Oecay ~atios are calculated from 30 seconds worth of data at a sample rate of 10 samples/second. This sample interval results in some inaccuracy in the decay ratio calculation, but provides rapid update in decay ratio data. A decay ratio of 0.75 is selected as a decay ratio limit for operator response such that sufficient margin to an instability occurrence is maintained. When operating in the region of applicability, decay ratio and peak-to-peak information shall be continuously calculated and displayed. A surveillance requirement to .
continuously monitor decay ratio and peak-to-peak noise values ensures rapid response such that changes in core conditions do not result in approaching a point of instability.
3/4.2.8 STABILITY MONITORING - SINGLE LOOP OPERATION The basis for stability monitoring during single loop operation is consistent with hat given above for two loop operation. The smaller size of the region of allowable operation, Region C, is due to a limit on the allowed I.
flow above the 80 rodline. When operating above the 80~ rodline in single loop operation, the core flow is required to be greater than 39Ã. < ~f'~ac << <j't-pq... Z ~e e~h.d (/e l'o-* ~g~ 0
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WASHINGTON NUCLEAR - UNIT 2 B 3/4 2-6 Amendment No. 84
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mmaoi<comev ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) 6.9.3.2 The analytical methods used to determine the core, operating limits shall be those topical reports and those revisions and/or supplements of the topical report previously reviewed and approved by the NRC, which describe the methodology applicable to the current cycle. For WNP"2 the topical. reports are:
- 1. ANF-1125(P)(A), and Supplements 1 and 2, "ANFB Critical Power Correlation," April 1990
- 2. Letter, R. C. Jones (NRC) to R. A. Copeland (ANF), "NRC Approval of ANFB Additive Constants for ANF 9x9-9X BWR Fuel," dated November 14, 1990
- 3. ANF-NF-524(P)(A), Revision 2 and Supplements 1 and 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors," November 1990
- 4. ANF-913(P)(A), Volume 1, Revision 1 and Volume 1, Supplements 2, 3 and 4, "COTRANSA 2: A Computer Program for Boiling Water Reactor Transient Analysis," August 1990
- 5. ANF-CC-33(P)(A), Supplement 2, "HUXY: A Generalized Multirod Heatup Code with 10 CFR 50, Appendix K Heatup Option," January 1991
- 6. XN-NF-80-19(P)(A), Volume 1, Supplements 3 and 4, "Advanced hic Nuclear Fuel Methodology for Boiling Water Reactors,"
November 1990
- 7. XN-NF-80-19(P)(A), Volume 4, Revision 1, "Exxon Nuclear Method-ology Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads," June 1986
- 8. XN-NF-80-19(P)(A), Volume 3, Revision 2, "Exxon Nuclear Method-ology for Boiling Water Reactors THERMEX: Thermal Limits Method-ology Summary Description," January 1987
- 9. XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," September 1986
- 10. ANF-89-014(P)(A), Revision 1 and Supplements 1 and 2, "Advanced Nuclear Fuels Corporation Generic Mechanical Design for Advanced Nuclear Fuels Corporation 9x9-IX and 9x9-9X BWR Reload Fuel,"
October 1991 XN-NF-81-22(P)(A), "Generic Statistical Uncertainty Analysis Methodology," November 1983 1O- uS
- 12. NEDE-24011-P-A- , "General Electric Standard Application fot Reactor Fuel,"
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)99 t WASHINGTON NUCL AR " UNIT 2 6-21 Amendment No. 9I, 109 c c llD&MQ pm+a M >~L~%Q
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- 13. EMF-CC-074 (P) (A), "Volume 1 STAIF A Computer Program for BWR Stability in the Frequency Domain, Volume 2 STAIF A Computer Program for BWR Stability in the Frequency Domain, Code Qualification Report", July 1994.
.ATTACHMENT4 STATE OF WASHINGTON )
Subject:
Request for Amendment to TS Power
) U te S i lementa Information COUNTY OF BENTON )
I, J. V. PARRISH, being duly sworn, subscribe to and say that I am the Assistant Managing Director, Operations for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that I have the full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information, and belief the statements made in it are true.
Attached to Supply System letter G02-93-249 dated October 8, 1993, "WNP-2 Request for Amendment to Technical Specifications to Increase Licensed Power Level, Supplementary Information," were three replacement pages to General Electric document NEDC-32141P, "Power Uprate With Extended Load Line Limit Safety Analysis for WNP-2," Class III, dated June-1993 which are considered-by their-owner to contain proprietary information.
The affidavit executed by Mr. David J. Robare, Project Manager, Plant Licensing General Electric Company, dated July 8, 1993, which provides the basis on which it is claimed that NEDC-32141P should be withheld from public disclosure under the provisions of 10 CFR 2.790 was provided as an attachment to Supply System letter G02-93-180, dated July 9, 1993, "WNP-2 Request for Amendment to Technical Specifications to Increase Licensed Power Level." This affidavit is also applicable to the replacement pages provided in the October 8, 1993, Supply System letter.
The Washington Public Power Supply System treats the replacement pages to NEDC-32141P attached to Supply System letter G02-93-180 dated July 9, 1993, as proprietary information on the basis of statements by its owner. In submitting this information to the NRC in support of the "WNP-2 Request for Amendment to Technical Specifications to Increase Licensed Power Level," the Supply System requests that the replacement pages to NEDC 32141P attached to Supply System letter 602-93-180 dated July 9, 1993, be withheld from public disclosure in accordance with 10 CFR 2.790.
DATE , 1994 J.. Parrish, Assistant Managing Director Operations On this date personally appeared before me J. V. PARRISH, to me known to be the individual who executed the foregoing instrument, and acknowledged that he signed the same as his free act and deed for the uses and purposes herein mentioned.
GIVEN under my hand and seal this day of 1994.
Notary Public in and for the STATE OF WASHINGTON Residing at Kennewick Washin on My Commission Expires
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