ML20212D361
| ML20212D361 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/21/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20212D358 | List: |
| References | |
| NUDOCS 9909230104 | |
| Download: ML20212D361 (12) | |
Text
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UNITED STATES pe g
j NUCLEAR REGULATORY COMMISSION o
' 1" WASHINGTON, D.C. 2056H001 s...../
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.168 TO FACILITY OPERATING LICENSE NO. DRP-63 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION, UNIT NO 1 DOCKET NO. 50-220
1.0 INTRODUCTION
By letter dated November 16,1998, as supplemented by letter dated June 21,1999, Niagara Mohawk Power Corporation (NMPC or the licensee) proposed a license amendment to change the Technical Specifications (TSs) for Nine Mile Point Nudear Station, Unit 1 (NMP1).
The proposed amendment would revise TSs related to the implementation of systems for the detection and suppression of coupled neutronic/ thermal-hydraulic instabilities in the reactor.
Average Power Range Monitor (APRM) flow control trip reference cards will initiate a reactor scram to limit the oscillation magnitude at reactor trip so as to limit the associated Critical Power Ratio (CPR) change and, in conjunction with Minimum Critical Power Ratio (MCPR) operating limits, assure compliance with the MCPR safety limit. In addition, the changes would increase the APRM flow biased neutron flux scram and control rod block settings to allow plant operation in the Extended Load Line Limit Analysis (ELLLA) region of the power / flow operating curve.
Thus, the proposed changes are in regard to setpoints and calculations for fuel cladding integrity. In TS 2.1.2a, the proposed change would be to the equation for determining the flow biased APRM scram and rod block trip setpoints. In Note (m) of TS Table 3.6.2/4.6.2, the proposed change would be to the calibration range for the APRM channel setpoint. In TS 6.9.1.f, which identifies documents approved by NRC for analytical methods used to determine core operating limits, the proposed change would add "NEDO-32465-A, Reactor Stability Detect and Suppress Solutions Licensing Basis MethorWogy for Reload Applications, August 1996."
In its submittal dated November 16,1998, NMPC identifies changes to the TS Bases that accompany the above TS changes. In the Bases for TS 2.1.1, the change references new equations in TS 2.1.2a. In the Bases for TS 2.1.2a, the change reflects the new setpoints. In the Bases for TS 2.2.2, the change is to the description of the setpoint methodology that is based upon General Electric (GE) Report NEDC-31336, "GE Instrumentation Setpoint Methodology." In the Bases for TS 3.6.2/4.6.2, the change is to the equations and methodology for determining APRM scram and rod block setpoints.
By letter dated June 21,1999, NMPC provided additional information in support of thc.
application for amendment. The additional information does not affect the Commission's finding of no significant hazards consideration that was issued in a Federal Reoister notice (63 FR j
71968, December 30,1998, as corrected by 64 FR 4148, January 27,1999).
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2.0 BACKGROUND
The principal purpose of the proposed amendment is to change the APRM flow biased scram settings to limit the reactor power oscillation magnitude during reactor trip, thereby limiting the associated CPR change and, in conjunction with MCPR operating limits, ensure compliance with the MCPR safety limit.
The change to the APRM flow biased neutron flux scram will be implemented by APRM Flow Control Trip Reference (FCTR) cards and by making the required changes to the APRM flow biased neutron flux scram (and rod block) TS. The FCTR cards implement the Enhanced Option I-A solution, which prevents reactor instabilities by automatically excluding reactor operations in regions of the power / flow operating domain that are susceptible to reactor power instabilities. The changes to the TS implement more restrictive TS flow biased scram trip (and rod block) settings in the low flow regions of the power / flow operating map (i.e., the operating conditions most susceptible to reactor instabilities).
In addition, the amendment would increase the APRM flow biased neutron flux scram and control rod block settings to allow plant operation in the previously approved ELLLA region.
l NMP1 is' currently restricted from full use of the ELLLA region of the power / flow map because of the flow biased rod block setpoints. The NRC staff previously approved operation in the ELLLA region by NMP1 Amendment No. 92, dated March 24,1987.
Existing NMP1 TS 2.1.2, " Fuel Cladding Integrity," applies to trip settings on automatic protective devices related to variables on which fuel safety limits have been placed. TS 2.1.2a delineates the relationships that establish the flow biased APRM scram and rod block trip settings. The maximum values of the scram and rod block trip settings are currently 120% and 110%,
respectively. NMPC has concluded from analyses that none of the postulated accidents would violate the established criteria with a 120% scram trip setting.
Reactor power level may be varied by moving control rods or by varying the recirculation flow rate. The APRM system provides a control rod block to prevent rod withdrawal beyond a given point at a constant recirculation flow rate. This rod block trip setting, which is automatically varied with recirculation flow rate, prevents an increase in the reactor power level to excessive values due to control rod withdrawal. The margin to the safety limit increases as the flow decreases for the specified trip setting versus flow relationship; therefore, the worst case MCPR which could occur during steady-state operation is at 1105. Of mtcd thermal power because of the APRM rod block trip setting.
The actual power distribution in the core is established by specified control rod sequences and is monitored continuously by the in-core local power range monitor (LPRM) system. As with the APRM scram trip setting, the APRM rod block trip setting is adjusted downward if the core maximum fraction of limiting power density exceeds the fraction of rated thermal power, thus, preserving the APRM rod block safety margin.
The current NMP1 APRM system consists of eight identical channels. Each channelis provided with eight inputs from the LPRM system to enable it to compute a core average thermal neutron i
flux, Additionally, the APRM averaging and trip circuits receive total recirculation flow signals and calculate the Reactor Protection System (scram) and the Reactor Manual Control System r
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l (control rod block) trip level setpoints in accordance with a specific relationship between core average power and total recirculation flow.
I NMP1 has been identified as a stability long-term solution Option ll plant, in which the existing quadrant-based APRM trip system, typical of BWR/2 plants, would initiate a reactor scram for a postulated reactor instability and avoid violating the MCPR safety limit. However, at NMP1, the TS flow biased APRM flux trip setting must be modified for Option 11 implementation. This change is required to limit the oscillation magnitude at reactor trip, thereby limiting the associated CPR change and, in conjunction with the MCPR operating limits, ensures operation within the MCPR Safety Limit. Specifically, changes to TS 2.1.2, " Fuel Cladding Integrity," are proposed. To implement this TS setting change, the eight APRM analog Flow Bias Trip Units were replaced with GE Nuclear Measurement Analysis and Control (NUMAC) Enhanced Option I-A (E1 A) digital FCTR cards. With these FCTR cards in place, a scram setpoint can be established that will meet General Design Criterion 12 of Appendix A to 10 CFR Part 50 for fuel design limit protection.
in the E1 A approach, prevention of reactor power instabilities is accomplished by automatically excluding reactor operations in regions of the power / flow operating domain that are susceptible to reactor power instabilities. Region I, the Exclusion Region, defines the limit of power and flow conditions that could result in reactor power instability during steady state operations. With the E1 A approach, any event that causes the reactor power-flow trajectory to cross into the exclusion region results in an automatic reactor trip, thereby preventing reactor operation in conditions susceptible to reactor instabilities.
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Region 11, the Restricted Region, defines the set of power and flow conditions within the reactor licensing basis that could result in reactor power instability if stability controls are not in place. A rod block feature prevents controlled entry into this region unless stability controls are in place.
Unintentional entry into Region ll results in an alarm, which alerts the operator to exit the region immediately. Within this region, a period-based detection system (PBDS) alerts the operator to l
an approach to reactor instability. Upon reaching a specified PBDS alarm, the operator is l
instructed to scram the reactor manually.
1 Region Ill, the Monitored Region, defines the operating envelope in which instabilities are only possible under conditions that exceed the reactor licensing basis (e.g., highly skewed power distributions that result in critical power ratio violations). The only requirement for operating in i
Region ill is that a period-based monitoring system be operable. Since this region bounds the area where instabilities are possible, no safety-related stability constraints are required outside Region Ill.
GENE-A13-00360-02," Application of Stability Long-Term Solution Option ll to Nine Mile Point Nuclear Station Unit 1," demonstrated the application of Option 11 methodology at NMP1 for operating Cycle 12. GENE-A13-00360-02 was submitted to the NRC by letter dated October 2, 1995. As indicated in GENE-A13-00360-02, " detect and suppress" calculations are partormad for two points along the rated rod line consistent with the Boiling Water Reactor Owners Group's (BWROG's) detect and suppress methodology (i.e., NEDO-32465, "BWR Owners' Group Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," dated May 1935). The accepted version, NEDO-32465-A, was issued in August 1996. The calculations start at MCPR Operating Limits along the rated rod line for (1) a five
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4-recirculation pump trip to natural circulation (i.e.,24.3% rated core flow) and (2) steady-state operation at 40% core flow. The five recirculation pump trip conservatively represents flow runback transients, including operation with one or two isolated recirculation loops. The 40%
core flow case conservatively represents plant startup conditions. In addition, GENE-A13-00360-02 documented the calculation of a revised Restricted Region boundary to be implemented at NMP1.
For Cycle 13, consistent with a 10 CFR Part 21 notification rnade by GE regarding Safety Limit MCPR evaluations (May 24,1996), NMPC performed a cycle specific safety limit MCPR calculation that resulted in a safety limit of 1.10 for five-loop and four-loop operation and a safety limit of 1.12 for three-loop operation. NMPC's detect and suppress methodology for NMP1 uses the higher of these safety limits as input to the calculations, resulting in a change to the GENE-A13-00360-02 Cycle 12 limits to Cycle 13 limits. The current MCPR Operating Limit at rated core flow on the rated rod line is less than or equal to 1.26 and the MCPR Operating Limit for steady state operation at 40% core flow on the rated rod line is less than or equal to 2.12. In addition, the Cycle 13 evaluation was based upon a base value for the reload batch size of 200 bundles, rather than the value stated in GENE-A13-00360-02.
The detect and suppress methodology applied to NMP1 was a simplification of the BWROG's detect and suppress methodology (NEDO-32465, May 1995). The NMP1 calculation used a combination of bounding and representative inputs to demonstrate with a deterministic calculation that the final MCPR value at oscillation suppression is greater than the MCPR safety limit. The inputs and assumptions used in the analysis to demonstrate MCPR safety limit protection resulted in restrictions on NMP1 APRM scram trip setpoints and MCPR operating limits for stability Option ll implementation. As indicated in GENE-A13-00360-02, the specific restrictions are:
- APRM trip analyticallimit at 24.3% flow s52.1% power APRM trip analytical limit at 40.0% flow s72.3% power a
The proposed change to the APRM flow biased neutron flux scram TS setpoints, (TS 2.1.2) implements the required settings. By letter dated August 19,1998, the NRC staff issued a safety evaluation regarding GENE-A13-00360-02 and NMPC's previous submittals responding to Generic Letter 94-02, "Long-Term Solutions and Upgrade of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in Boiling Water Reactors." The NRC found that GENE-A13-00360-02 was acceptable for use by NMPC.
I The APRM flow-biased trip setpoint is currently being maintained within both the current TSs as well as within the setpoint determined in NRC accepted GENE-A13-00360-02 to preclude instabilities. Accordingly, the FCTR cards are currently operational to implement Stability Solution Option 11. The proposed changes will revise the TS APRM flow-biased trip setpoint to be consistent with GENE-A13-00360-02. The MCPR operating limits will be maintained in the Core Operating Limits Report. The margin between the APRM flow biased neutron flux scram and the APRM flow biased control rod block was determined via calculation (GENE-C5100196-04, "APRM Flow-Biased Trip Setpoints Stability Long-Term Solution Option ll," dated June 1997).
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TS Section 6.9.1.f, " Core Operating Limits Report," subsection 2, lists the documents that i
describe the analytical methods used to determine the core' operating limits, that have been reviewed and approved by the NRC. NEDO-32465-A, " Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996, meets these criteria and, therefore, will be added to Section 6.9.1.f.
3.0 EVALUATION l
The proposed amendment would change (1) TS 2.1.2 regarding the flow biased APRM scram l
and rod block trip settings, (2) Note (m) to Table 4.6.2a concerning channel accuracy, and (3)
TS 6.9.1.f. The NRC staff's evaluation of each of these changes is presented in the following subsections.
In its submittal, NMPC also provided associated changes to the TS Bases for sections 2.1.1, 2.1.2,2.2.2,3.6.2, and 4.6.2. Pursuant to 10 CFR 50.36(a), TS Bases are not part of the TS (i.e., not an integral part of the operating license). These changes are described below for clarity and completeness.
3.1 TS 2.1.2. " Fuel Claddina Intearity." (TS Daae 9)
NMPC proposes to replace the flow biased APRM scram and rod block trip settings in TS 2.1.2.a with the following equations:
"The minimum of:
1 For W > Om l
l S 5 (0.55W + 67%)T with a maximum value of 122%
Sne s (0.55W + 62%)T with a maximum value of 117%
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AND:
For 18% s W < 40%:
i S s (1.287W + 20.83%)
Saas (1.287W + 13.54%)"
WHERE:
S or Sne = The respective scram or rod block setpoint W = Loop recirculation flow as a percentage of the loop recirculation flow which produces a rated core flow of 67.5 MLB/HR T = FRTP/CMFLPD (T is applied only if less than or equal to 1.0)
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6-FRTP = Fraction of rated thermal power where rated thermal power equals 1850 MW CMFLPD = Core maximum fraction of limiting power density NMPC indicated that the proposed changes to the APRM flow biased neutron flux scram setting are needed: 1) to allow plant operation in the ELLLA region, which the NRC staff previously approved by Amendment No. 92 dated March 24,1987; and 2) to limit the oscillation magnitude at reactor trip in the low flow regions of the power / flow operating map.
i The NRC staff has reviewed this request for TS changes and finds that the approved methodologies addressed by GENE-A13-00360-02 and License Amendment No. 92 were applied to the proposed changes to the APRM flow biased neutron flux scram and control rod block settings in the low-flow regions to limit the oscillation magnitude at reactor trip and in the high-flow regions to allow plant operation in the previously approved ELLLA region. The NRC staff also finds that Chapter 15 analyses of the Standard Review Plan (i.e., NUREG-0800) indicate satisfactory results for an increase in the analytical limits of 2 percent for the APRM flow-biased scram and 7 percent for the control rod block. NMPC further justified the selection of the 2 percent increase to the APRM scram analytical lirnit based upon acceptable results of analysis performed by GE (see Memorandum by D. Hood, " Electronic Mail Regarding Proposed License Amendment on Nine Mile Point Nuclear Station, Unit No.1," dated August 6,1999). On the basis of these acceptable results, the NRC staff finds the proposed changes to TS 2.1.2 to be acceptable.
3.2 Bases I J 2.1.1. " Fuel Claddina - Safetv Limit." (TS oace 14)
The Bases fo 9 2.1.1 currently states, in part, that: "During steady-state operation at lower power levels, where the fraction of rated thermal power is less than the core maximum fraction of limiting power density, the APRM flow biased scram and rod block settings are adjusted by the equation in Specification 2.1.2a." In the revised Bases, the word " equation"in this sentence is changed to " equations". This change corresponds to the proposed TS changes stated in 3.1 above.
3.3 Bases For TS 2.1.2. " Fuel Claddina Limitina Safety System Settina."(TS Daaes 17.18.19.
and 22)
The Bases for TS 2.1.2 (see TS page 17) currently states, in part, that: " Analyses (5 8 8 8 ' ' )
demonstrate that with a 120% scram trip setting, none of the abnormal operational transients analyzed violate the fuel safety limit and there is a substantial margin from fuel damage." In the revised Bases, NMPC has added an additional reference, Reference 18, to this sentence.
Reference 18 refers to GENE-C5100196-04,"APRM Flow-Biased Trip Setpoints Stability Long-j Term Solution Option 11," dated June 1997. NMPC also changed the specified scram trip setting of "120%" to "122%"
l NMPC has supplemented the Bases for TS 2.1.2 by adding the following new paragraph to TS page 18: "Also, a scram setting has been established te preclude thermal-hydraulic instabilities l
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.... which could compromise fuel safety limits. Specifically, the scram setting will limit the oscillation magnitude at reactor trip, thereby limiting the associated CPR change, and in conjunction with MCPR operating limits, assure compliance with the MCPR safety limit."
The Bases for TS 2.1.2 currently states, on TS page 18, that "The margin to the safety limit increases as the flovir decreases for the specified trip setting versus flow relationship; therefore, j
the worst case MCPR which could occur during steady-state operation is at 110% of rated thermal power because of the APRM rod block trip setting." NMPC has changed the "110%"in this sentence to "117%."
On TS page 19, the Bases for TS 2.1.2 currently states that "The adequacy of the IRM
[ Intermediate Range Monitor) scram in range 10 was determined by comparing the scram level on the IRM range 10 to the minimum APRM scram level. The IRM scram is at approximately 38.4% of rated neutron flux while the minimum flow biased APRM scram which occurs at zero recirculation flow is at 65% of rated power." These sentences are changed to state: "The adequacy of the IRM scram in range 10 (approximately 38.4% of rated neutron flux) was determined by comparing the scram level on the IRM range 10 to the minimum APRM scram level for transient protection. The APRM scram level for transient protect;on is defined by the Section 2.1.2a equation for W 2 0%. This equation results in a minimum APRM scram of 67%
of rated power at zero recirculation flow."
On TS page 22, which is a list of references for Bases 2.1.1 and 2.1.2, the change adds Reference "(18) GENE-C5100196-04, 'APRM Flow-Biased Trip Setpoints Stability Long-Term Solution Option 11,' dated June 1997."
3.4 Bases For 2.2.2. " Reactor Coolant System - Limitina Safety System Settina."(TS oaae26)
Section C of the Bases for 2.2.2 discusses the APRM trip and currently states, in part, that "Although the operator will set the scram setting at less than or equal to that required by
- Specification 2.1.2a, the actual neutron flux setting can be as much as 2.7 percent of rated neutron flux above the specified value. This includes the errors discussed above." These sentences are changed to state: "For the APRM scram, the setpoint has been derived based on GE setpoint methodology as outlined in NEDC-31336, 'GE Instrumentation Setpoint Methodology.' In this methodology, the setpoint is defined as three values, Nominal Trip Setpoint, Allowable Value, and Analytical Limit. The operator will set the Nominal Trip Setpoint.
The Allowable Value is listed in the Bases for Specifications 3.6.2 and 4.6.2. The analyticallimit is listed in Specification 2.1.2a."
3.5 Notes For Table 4.6.2a. " Instrumentation That initiates Scram." (TS oaae 203)
Table 4.6.2a indicates surveillance requirements for instrumentation that initiates scram. It shows under the neutron flux parameters for "APRM Upscale," an instrument channel calibration is to be performed once per week, and uses Note (m) to amplify this requirement. Note (m) states, in part," Adjust the APRM channelif the absolute difference is greater than 2% of RATED THERMAL POWER. Any APRM channel gain adjustment made in compliance with Specification 2.1.2a shall not be included in determining the absolute difference." The proposed changes would delete the words " absolute" (which occurs twice), and would replace L
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"2%" with "+2.0/-1.9%." These changes reflect the APRM channel accuracy tolerance which is more conservative. Therefore, the NRC staff finds the proposed changes to be acceptable.
L 3.6 Bases for 3.6.2 and 4.6.2. " Protective Instrumentation."(TS oaae 251)
The Bases for 3.6.2 and 4.6.2 currently indicatee the maximum allowable setpoint deviations to be: "APRM Scram, +/- 2.3% of rated neutron flux (analyticallimit is 120% of rated flux). APRM Rod Block, +/- 2.3% of rated neutron flux (analytical limit is 110% of rated flux)." This is changed to state: "The APRM scram and rod block setpoints have been derived based on GE setpoint methodology as outlined in NEDC-31336, 'GE Instrumentation Setpoint Methodology.'
In this methodology, the setpoints are defined as three values, Nominal Trip Setpoints, Allowable Values, and Analytical Limits. The analytical limits are listed in Specification 2.1.2a.
The allowable values are listed below:
The minimum of:
For W > 0%:
S s (0.55W + 64.46%)T with a maximum value of 119.5%
Sne s (0.55W + 59.46%)T with a maximum value of 114.5%
AND:
- For 14.42% < W s 45%:
S s (1.287W + 16.6%)
Sne s (1.287W + 9.312%)
WHERE:
S or Sas= The respective scram or rod block allowable value W = Loop. recirculation flow as a percentage of the loop recirculation flow which
)
produces a rated core flow of 67.5 MLB/HR T = FRTP/CMFLPD (T is applied only if less than or equal to.1.0)
FRTP = Fraction of Rated Thermal Power where Rated Thermal Power equals 1850MW i
CMFLPD = Core Maximum Fraction of Limiting Power Density" J
3.7 TS 6.9.1.f. "Reportina Reauirements--Routine Reports--Core Operatina Limits Report."
(TS Daae 367)
TS Section 6.9.1.f, " Core Operating Limits Report," subsection 2, states that the analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC. The subsection currently lists three documents and the proposed change would add a fourth--NEDO-32465-A, " Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," dated August 1996. The NRC staff finds that this document has been approved previously by the NRC staff and that its addition to the list is appropriate and acceptable, m
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4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative -
occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (63 FR 71968, as corrected by 64 FR 4148). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 ' CONCLUSION The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the
. common defense and security or to the health and safety of the public.
Principal Contributors: M. Waterman T. Huang D. Hood Date: September 21, 1999 l
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,Y DATED:
Seotember 21. 1999 AMENDMENT NO.168TO FACILITY OPERATING LICENSE NO. DPR-63 NINE MILE POINT NUCLEAR POWER STATION UNIT NO.1 MW62iEP PUBLIC PDI-1 Reading S. Bajwa S. Little D. Hood OGC G. Hill (2), T-5 C3
M. Waterman E. Marinos T. Huang J. Wermiel cc: Plant Service list
[l Mr. John H. Mu:ll:r '
September 21, 1999 g
Chl:.f Nucl=r Offic:r i
Nirg:rs Mohrwk Power Corporation Nine Mile Point Nuclear Station
,.,s Operations Building, Second Floor P.O. Box 63 Lycoming, NY 13093
SUBJECT:
ISSUANCE OF AMENDMENT FOR NINE MILE POINT NUCLEAR STATION, UNIT NO.1 (TAC NO. MA4218)
Dear Mr. Mueller:
The Commission has issued the enclosed Amendment NoJ 68to Facility Operating License No.
DPR-63 for the Nine Mile Point Nuclear Station, Unit No.1. The amendment consists of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated November 16,1998, as supplemented by letter dated June 21,1999.
This amendment changes the TSs regarding the setpoints for the average power range monitor flow biased scram to limit the magnitude of reactor power oscillations during a reactor trip, and along with changes to the control rod block settings, allow for operation in the Extended Load Line Limit Analysis region of the power / flow operating curve.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Reaister Notice.
Sincerely, Original signed by:
barl S. Hood, Sr. Project Manager, Section 1 Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-220
Enclosures:
- 1. Amendment No.168to DRP-63
- 2. Safety Evaluation cc w/encis: See next page DOCUMENT NAME: G:\\PDI-1\\NMP1\\AMDA4218.WPD TO receive a copy of this document, Indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with ettachment/ enclosure "N" = No copy 0FFICE PM:P01 m gi lE LA:PDlJQ l
SC:PDI /@
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DATE q / C/ /99 9 / 8 /99 4 / fd//99 9 / / /99
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Official Record Copy I
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DATED:
September 21. 1999 AMENDMENT NO.168 TO FACILITY OPERATING LICENSE NO. DPR-63 NINE MILE POINT NUCLEAR POWER STATION UNIT NO.1 Docket Filo PUBLIC PDI-1 Reading S. Bajwa S. Little D. Hood OGC G. Hill (2), T-5 C3 W. Beckner ACRS M. Oprendek, Region l R. Scholl(e-mail SE only to RFS)
M. Waterman E. Marinos T. Huang J. Wermiel cc: Plant Service list