ML17278A376

Amend 16 to License NPF-21,changing & Adding Tech Specs to Explain Basis for Surveillance on Neutron Flux Noise Levels So That Max Allowable Safe Power Level Relates to Core Coolant Flow Rate

ML17278A376
Person / Time
Site:	Columbia
Issue date:	09/05/1985
From:	Butler W Office of Nuclear Reactor Regulation
To:
Shared Package
ML17278A377	List: ML17278A376 ML17278A378
References
TAC-59235, NUDOCS 8509110431
Download: ML17278A376 (26)

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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 WPPSS NUCLEAR PROJECT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE License No. NPF-21 Amendment No.

16 1.

The Nuclear Regulatory Commission (the Commission or the NRC) has found that:

A.

The application for amendment filed by the Washington Public Power Supply System (the Supply System, also the licensee) dated July 17 and 19, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application as

amended, the provisions of the Act, and the regulations of the Commission; C.

There is reasonable assurance:

(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulation set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or the health and safety of. the public; arrd E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, Facility Operating License No. NPF-Zl is amended to revise the Technical Specifications as indicated in the attachment to this amendment and paragraph 2.C.(2) of the Facility Operating License is hereby amended to read as follows:

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 16, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

8509110431 850905 PDR'ADDCK 05000397

,P

-". 'DR

3.

This amendment is effective as of July 19, 1985

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FOR THE NUCLEAR REGULATORY COtlNISSION

Enclosure:

Changes to ihe Technical Specifications Date of Issuance:

SKP 0 >

Walter R ~ Butl'er, Chief Licensing Branch No.

2 Division of Licensing

ATTACHMENT TO LICENSE AMENDMENT,NO. 16 FACILITY OPERATING LICENSE NO. NPF-21 DOCKET NO. 50-397 Replace the following pages of the Appendix "A" Technical Specifications with enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

REMOVE V1 X111 X1X XX 3/4 4-1 3/4 4-2 3/4 4-3 W

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W 83/4 3-7 83/4 3-7a INSERT Vj X111 X1X XX 3/4 3-102 3/4 3-103 3/4 3-104 3/4 4-1 3/4 4-2 3/4 4-3 3/4 4-3a 83/4 3-7 83/4 3-7a

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I INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION 3/4. 3 INSTRUMENTATION PAGE 3/4.3. 1 3/4. 3. 2 3/4.3.3 3/4. 3. 4 REACTOR PROTECTION SYSTEM INSTRUMENTATION............

ISOLATION ACTUATION INSTRUMENTATION..................

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION..:...................................

RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION 3/4 3-1 3/4 3-10 3/4 3-25 ATWS Recirculation Pump Trip System Instrumentation..

3/4 3-37 3/4. 3. 5 3/4.3.6 3/4. 3. 7 3/4. 3. 8 End-of-Cycle Recirculation Pump Trip System Instrumentation........................

REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION....................................

CONTROL ROD BLOCK INSTRUMENTATION..................

MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation...............

Seismic Monitoring Instrumentation.

Meteorological Monitoring Instrumentation............

Remote Shutdown Monitoring Instrumentation...........

Accident Monitoring Instrumentation..................

Source Range Monitors...............

Traversing In-Core Probe System......................

Chlorine Detection System..............

Fire Detection Instrumentation.........

Loose-Part Detection System...............

Radioactive Liquid Effluent Monitoring Instrumentation.

Radioactive Gaseous Effluent Monitoring Instrumentatson.........................

TURBINE OVERSPEED PROTECTION SYSTEM.

3/4 3-41 I

3/4 3-47 3/4 3"52 3/4 3-58 3/4 3-61 3/4 3-64 3/4 3-67 3/4 3-70 3/4 3-76 3/4 3-77 3/4 3-78 3/4 3-79 3/4 3"83 3/4 3-84 3/4 3-89 3/4 3-96 3/4. 3. 9 FEEDWATER SYSTEM/MAIN TURBINE TRIP SYSTEM INSTRUMENTATION............ ~....

3/4. 3. 10 NEUTRON FLUX. MONITORING INSTRUMENTATION WASHINGTON NUCLEAR - UNIT 2 vl ACTUATION 3/4 3"98

'3/4 3"102 Amendment No.

16

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INOEX BASES Radioactive Liquid Eff1uent Monitoring Instrumentation.............................

Radioactive Gaseous Eff1uent Monitoring Instrumentation.............................

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3/4. 3. 8 3/4. 3. 9 TURBINE OVERSPEED PROTECTION SYSTEM..............

FEEDMATER SYSTEM/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION....

3/4. 3. 10 NEUTRON FLUX MONITORING INSTRUMENTATION........-

3/4.4 REACTOR COOLANT SYSTEM 3/4.4. 1 RECIRCULATION SYSTEM........................:...

3/4.4. 2 SAFETY/RELIEF VALVES.............................

3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE SECTION INSTRUMENTATION (Continued) 3/4.3. 7 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation........

Seismic Monitoring Instrumentation..........

Meteoro1ogica1 Monitoring Instrumentation...

Remote Shutdown Monitoring Instrumentation..

Accident Monitoring Instrumentation.........

Source Range Monitors...........................

Traversing In-Care Probe System.................

Chlorine Detection System.......

Fire Detection Instrumentation..

Loose-Part Detection System.....................

PAGE 8 3/4 3-4 8 3/4 3-4 8 3/4 3"5 8 3/4 3-5 8 3/4 3-5 8 3/4 3"5 8 3/4 3-5 8 3/4 3 5 8 3/4 3-6 8 3/4 3-6 8 3/4 3-6 8 3/4 3-7 8 3/4 3"7 8 3/4 3-7 8 3/4 3-7 8 3/4 4"1 8 3/4 4-1 3/4.4. 4 Leakage Detection Systems.

Operationa1 Leakage..

CHEMISTRY........

8 3/4 4"2 8 3/4 4-2 8 3/4 4-2 3/4.4.5 SPECIFIC ACTIVITY....................

8 3/4 4-3 3/4.4. 6 PRESSURE/TEMPERATURE LIMITS.....................

8 3/4 4"4 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES................

8 3/4 4"5 MASHINGTON NUCLEAR - UNIT 2 X111 Amendment No.

16

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INDEX ADMINISTRATIVE CONTROLS SECTION CORPORATE NUCLEAR SAFETY REVIEW BOARD (Continued)

CONSULTANTS

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R PAGE 6-11 6"ll 6-11 6"12 6-13 6.6 REPORTABLE OCCURRENCE ACTION..............................

6-13

6. 7 SAFETY LIMITVIOLATION....................................

6.8 PROCEDURES AND PROGRAMS...................................

6-14.

6-14 6.9 REPORTING RE UIREMENTS..................................

6-16 6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES...........

6-16 STARTUP REPORT.......................................

ANNUAL REPORTS......................,.."...........'...

6-16 6"16 MONTHLY OPERATING REPORTS.

6-17 REPORTABLE OCCURENCES.........

~......................

6-17 PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP............

6-17 THIRTY DAY WRITTEN REPORTS...........................

6-19 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT, 6"20 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT.......

6-21 6.9.2 SPECIAL REPORTS................

6. 10 RECORD RETENTION.................

6. 11 RADIATION PROTECTION PROGRAM........

6. 12 HIGH RADIATION AREA.............

6. 13 PROCESS CONTROL PROGRAM.....

6"22 6"22 6-24 6-24 6-25

6. 14 OFFSITE DOSE CALCULATIONMANUAL..........................

6-25 6.15 MAJOR CHANGES TO RADIOACTIVE LI UID GASEOUS AND SOLID WASTE TREATMENT SYSTEMS............................

6-26 WASHINGTON NUCLEAR - UNIT 2 Xix Amendment No.

16

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LIST OF FIGURES INOEX FIGURE 3.1. 5-1

3. l. 5-2 3 ~ 2e 1 1 3.2. lee2 3e 2 ~ 1 3 3 ~ 2e 3 1 3.3.10-1 3.4. 1. 1-1 3.4 6.1"1 3.4. 6. 1-2

4. 7"1

3. 9. 7"1 PAGE SODIUM PENTABORATE SOLUTION SATURATION TEMPERATURE...

~34 1-21 SODIUM PENTABORATE TANK, VOLUME VERSUS CONCENTRATION REQUIREMENTS.........................................

3/4 1-22 MAXIMUMAVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE, INITIALCORE FUEL TYPE 8CR183........................

3/4 2-2 MAXIMUMAVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VERSUS AVERAGE PLANAR EXPOSURE, INITIAL CORE FUEL TYPE 8CR233........................

3/4 2-3 MAXIMUMAVERAGE PLANAR LINEAR HEAT GfNERATION RATE (MAPLHGR)- VERSUS AVERAGE PLANAR EXPOSURE, INITIAL CORE FUEL-TYPE 8CR711........................

3/4 2-4 MINIMUM CRITICAL POWER RATIO (MCPR)

K~ FACTOR VERSUS CORE FLOW...................

3/4 2-7 THERMAL POWER LIMITS OF SPEC. 3.3.10-1...............

3/4 3-104 THERMAL POWER LIMITS OF SPEC. 3.4.1.1-1.......;......

3/4 4-3a MINIMUM REACTOR VfSSEL MfTAL TEMPERATURE VERSUS REACTOR VESSEL PRESSURE (INITIALVALUES)......

3/4 4-20 MINIMUM REACTOR VESSEL METAL TEMPERATURE VERSUS REACTOR VESSEL PRESSURE (OPERATIONAL VALUES). ~.......

3/4 4-21 SAMPLE PLAN 2)

FOR SNUBBER FUNCTIONAL TEST..........

3/4 7-15 WfIGHT/HEIGHT LIMITATIONS FOR LOADS OVER THE SPENT FUEL STORAGE POOL..................

3/4 9-10 B 3/4 3-1 B 3/4.4.6-1 REACTOR VESSEL WATER LEVEL..................

FAST NEUTRON FLUENCE (E)lMeV) AT 1/4 T AS A FUNCTION OF SERVICE LIFE......

B 3/4 3-8 B 3/4 4"7

5. leel

5. 1-2

5. 1-3 LOW POPULATION ZONE...............

5"3 UNRESTRICTED ARfAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS.............

5"4 EXCLUSION AREA BOUNDARY......................;.

5-2

6. 2. 1"1

6. 2. 2-la

6. 2. 2-lb OFFSITE ORGANIZATION..................

UNIT ORGANIZATION......

UNIT ORGANIZATION " OPERATIONS DEPARTMENT...

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6 5 WASHINGTON NUCLEAR UNIT 2 XX Amendment No.

16

INSTRUMENTATION 3/4.3.10 NEUTRON FLUX MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.10 The APRM and LPRM" neutron flux noise levels shall not exceed three (3) times their established baseline value.

APPLICABILITY:

OPERATIONAL CONOITION I with two reactor cooiant. system recir-culation loops in operation with THERMAL POWER greater than the limit specified

'in Figure 3.3.10-1 and total core flow less than 45K of rated total core flow or with one reactor coolant system recirculation loop not in operation with THERMAL POWER greater than the limit specified in Figure 3.3.10-1.

ACTION:

With the APRM or LPRM" neutron flux noise level greater than three (3) times their established baseline noise levels, initiate corrective action within 15 minutes to restore the noise levels to within the required limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than or equal to the limit specified in Figure 3.3.10"1 within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

SURVEILLANCE RE UIREMENTS 4.3.10.1 The provisions of Specification 4.0.4 are not applicable.

4.3.10.2 With two reactor coolant system recirculation loops in operation, establish a baseline APRM and LPRM" neutron flux noise level value within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> upon entering the APPLICABLE OPERATIONAL CONDITION of Specifica-tion 3.3.10 provided that baselining has not been performed since the most recent CORE ALTERATION.

4.3.10.3 With one reactor coolant system recirculation loop not in operation, establish a baseline APRM and LPRM* neutron flux noise level value with THERMAL POWER less than ot equal to the limit specified in Figure 3.3. 10-1 prior to entering the APPLICABLE OPERATIONAL CONDITION of Specification-3.3.10 provided baselining has not been performed with one reactor coolant system recirculation loop not in operation since the most recent CORE ALTERATION.S WASHINGTON NUCLEAR - UNIT 2 3/4 3-102 Amendment No.

16

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INSTRUMENTATION NEUTRON FLUX MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS Continued 4.3.10.4 The APRM and LPRM" neutron flux noise levels shall be determined to be less than or equal to the limit of Specification 3.3.10 when operating within the APPLICABLE OPERATIONAL CONDITION of Specification 3.3.10:

a.

At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and b.

. Within 30 minutes after completion of a THERMAL POWER increase of at least 5X of RATED THERMAL POWER.

"Detector levels A and C of one LPRM string per core octant plus detector levels A and C of one LPRM string in the center of the core should be monitored.

¹The baseline data obtained in Specification 4.3. 10.3 is applicable to opera-tion with one reactor coolant system recirculation loop not in operation and THERMAL POWER greater than the limits specified in Figure 3.3.10-1.

WASHINGTON NUCLEAR - UNIT 2 3/4 3-103 Amendment No.

16

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FIGURE 3.3.10-1 THERMAL POWER I IMITS OF SPECIFICATION 3.3.10-1 70 60 50 40 30 C) 20 10 0

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3/4.4 REACTOR COOLANT SYSTEM 3/4.4. 1 RECIRCULATION SYSTEM RECIRCULATION LOOPS LIMITING CONDITION FOR OPERATION 3.4.1.1 Two reactor coolant system recirculation loops shall be in operation.

APPLICABILITY:

OPERATIONAL CONDITIONS 1" and-2~;

ACTION:

a \\

With one reactor coolant system recirculation loop not in operation:

l.

Within 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />s:

a)

Place the recirculation flow control system in the Local Manual (Position Control) mode, and b)

The THERMAL POWER shall be less than or equal to the limit specified in Figure 3.4.1. 1-1 or the provisions of Specifi-cation 4.3.10.3 are satisfied.

With one reactor coolant system recirculation loop not in operation and with THERMAL POWER greater than the limit specified in Figure 3.4.1. 1-1, and the provisions of Specification 4.3.10.3 having not been satisfied, initiate action within 15 minutes to reduce THERMAL POWER to less than or equal to the limit specified in Figure 3.4. 1. 1-1 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

The provisions of Specification 4.3.10.3 must be satisfied prior to resuming power operation above the limit specified in Figure 3.4.1.1-1.

c)

Increase the MINIMUM CRITICAL POWER RATIO (MCPR) Safety Limit by 0.01 to 1.07 per Specification 2.1.2,

and, d)

Reduce the Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) limit to a value of 0.84 times the two recirculation loop operation limit per Specification 3.2. 1,

and, e)

Reduce the Average Power Range Monitor (APRM) Scram and Rod Block and Rod Block Monitor Trip Setpoints and Allow-able Values to those applicable for single recirculation loop operation per Specifications 2.2.1, 3.2.2, and 3.3.6.

f)

Reduce the volumetric flow rate of the operating recircula-tion loop to < 41,725"" gpm.

1 111 1*

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""This value represents the actual volumetric recirculation loop flow which produces 100X core flow at 100K THERMAL POWER.

This value was determined during the Startup Test Program.

WASHINGTON NUCLEAR - UNIT 2 3/4 4"1 Amendment No.

16

REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION Continued ACTION:

(Cnntinued) g)

Perform Surveillance Requirement 4.4.1.1.2 if THERMAL POWER is < 25K*"" of RATED THERMAL POWER or the recirculation loop flow.in the operating loop is < lOX"*"of rated loop flow.

h)

Reduce recirculation loop flow in the operating loop until the core plate 4P noise does not deviate from the estab-lished core plate hP noise patterns by more than 100K.

i)

With one reactor coolant system recirculation loop not in operation and THERMAL POWER greater than the limit speci-fied in Figure 3.4.1.1-1 and core flow less than 39K of rated core flow, initiate action within 15 minutes to reduce THERMAL POWER to less than or equal to the limit specified in Fig. 3.4.1.1-1 or increase core flow to greater than or equal to 39K of rated core flow within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

2.

The provisions of Specification 3.0.4 are not applicable.

3.'therwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

With no reactor coolant system recirculation loops in operation, immediately initiate measures to place the unit in at least HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEII LANCE RE UIREMENTS 4.4.1.1.1 With one reactor coolant system recirculation loop not in operation, at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> verify that:

a.

The recirculation flow control system is in the Local Manual (Position Control) mode, and b.

The volumetric flow rate of the operating loop is

< 41,725 gpm."*

• ~This value represents the actual volumetric recirculation loop flow which produces 100X core flow at 100K THERMAL POWER.

This value was determined during the Startup Test Program.

"*"Final values were determined during Startup Testing based upon actual THERMAL POWER and recirculation loop flow which will sweep the cold water from the vessel bottom head preventing stratification.

WASHINGTON NUCLEAR UNIT 2 3/4 4"2 Amendment No.

16

f f,f

REA TOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS Continued c.

The core plate hP noise is less than 200K of the established core plate AP noise patterns.

d.

Core flow is greater than or equal to 39K of rated core flow when core THERMAL POWER is greater than the limit specified in Figure 3.4.1.1-1.

4.4.1.1.2 With one reactor coolant system recirculation loop not in operation, within no more than 15 minutes prior to either THERMAL POWER increase or recir-culation loop flow increase, verify that the following differential temperature requirements are met if THERMAL POWER is

< 25X""" of RATED THERMAL POWER or the t

recirculation loop flow in the operating recirculation loop is

< 10K"*" of rated ]

loop flow:

a.

< 145 F between reactor vessel steam space coolant and bottom head drain line coolant, b.

C.

< 50 F between the reactor coolant within the loop not in operation and the coolant in the reactor pressure

vessel, and

< 50 F between the reactor coolant within the loop not in operation and the operating loop.

The differential temperature requirements of Specification 4.4.1.1.2b.

and c.

do not apply when the loop not in operation is isolated from the reactor pressure vessel.

4.4.1.1.3 Each reactor coolant system recirculation loop flow control valve shall be demonstrated OPERABLE at least once per 18 months by:

a.

Verifying that the control valve fails "as is" on loss of hydraulic pressure (at the hydraulic control unit), and b.

Verifying that the average rate of control valve movement is:

1.

Less than or equal to 13K of stroke per second

opening, and 2.

Less than or equal to 11K of stroke per second closing.

"**Final values were determined during Startup Testing based upon actual THERMAL POWER and recirculation loop flow which will sweep the cold water from the vessel bottom head preventing stratification.

WASHINGTON NUCLEAR UNIT 2 3/4 4-3 Amendment No.

16

M I

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INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Continued) 3/4.3.7.12 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential-releases of gaseous,effluents.

The alarm/

trip setpoints for these instruments shall be calculated and adjusted in ac-cordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20.

This instrumentation also includes provisions for monitoring and controlling the concentrations of potentially explosive gas mixtures in the WASTE GAS HOLDUP SYSTEM.

The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.

3/4.3.8 TURBINE OVERSPEED PROTECTION SYSTEM This specification is provided to ensure that the turbine overspeed protection system instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed.

Protection from turbine excessive overspeed.is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety-related components, equipment or structures.

3/4.3.9 FEEDWATER SYSTEM/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION The feedwater system/main turbine trip. system actuation instrumentation is provided to initiate the feedwater system/main turbine trip system in the event of reactor vessel water level equal to or greater than the level 8

setpoint associated with a feedwater controller failure.

3/4.3.10 NEUTRON FLUX MONITORING INSTRUMENTATION At the high power/low flow corner of the operating

domain, a small prob-ability of limit cycle neutron flux oscillations exists depending on combina-tions 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 noise levels should be monitored while operating in this region.

Stability tests at operating BWRs were reviewed to determine a generic region of the power/floe map in which surveillance of neutron flux noise levels should be performed.

A conservative decay ratio of 0.6 was chosen as the bases 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 greater than that specified in Figure 3.4. l.,l-l (Reference).

WASHINGTON NUCLEAR " UNIT 2 B 3/4 3-7 Amendment No.

16

INSTRUMENTATION BASES MONITORING INSTRUMENTATION (Conti nued)

NEUTRON FLUX MONITORING INSTRUMENTATION (Continued)

Neutron flux noise limits are also established to ensure early detection of. limit cycle neutron flux oscillations.

BWR cores typically operate with neutron flux noise caused by random boiling and flow noise.

Typical neutron flux noise levels of 1-12X of rated power (peak-to-peak) have been reported for the range of low to high recirculation loop flow during both single and dual recirculation loop operation.

Stability tests at operating BWRs have demon-strated that when stability related neutron flux limit cycle oscillations occur they result in peak-to-peak neutron flux limit cycles of 5-10 times the typical values.

Therefore, actions taken to reduce neutron flux noise levels exceeding three (3) times the typical value are sufficient to ensure early detection of limit cycle neutron flux oscillations.

Typically, neutron flux noise levels show a gradual increase in absolute magnitude as core flow is incieased (constant control rod pattern) with two reactor recirculation loops in operation.

Therefore, the baseline neutron flux noise level obtained at a specific core flow can be applied over a range of core flows.

To maintain a reasonable, variation between the low flow and high flow ends of the flow range, the range over. which a specific baseline is applied should not exceed 20'f rated core flow with two recirculation loops in opera-tion.

Data from tests and operating plants indicate that a range of 20X of rated core flow will result in approximately a 50K increase in neutron flux noise level during operation with two recirculation loops.

Baseline data should be taken near the maximum rod line at which the majority of operation will occur.

However, baseline data taken at lower rod lines (i.e., lower. power) will result in a conservative value since the neutron flux noise level is proportional to the power level at a given core flow.

In the case of single loop operation (SLO), the normal neutron flux noise may increase more rapidly when reverse flow occurs in the inactive jet pumps.

This justifies a smaller flow range under high flow SLO conditions.

Baseline data should be taken at flow intervals which correspond to less than a 50K in-crease in APRM neutron flux noise level. If baseline data are.not specifically available for SLO, then baseline data with two recirculation loops in operation can be conservatively applied to SLO since for the same core flow SLO will exh'ibit higher neutron flux noise levels than operation with two loops.

However, because of reverse flow characteristics of SLO, the core flow/drive flow re-lationship is different than the two loop relationship and therefore the base-line data for SLO should be based on the active loop recirculation drive flow, and not the core flow.

Because of the uncertainties involved in SLO at high reverse flows, baseline data should be taken at or below the power specified in Figure 3.4. l. 1-1.

This will result in approximately a 25X conservative baseline value if compared to baseline data taken near the rated rod line and will therefore not result in an overly restrictive baseline value, while

, providing sufficient margin to 'cover uncertainties associated with SLO.

WASHINGTON NUCLEAR - UNIT 2 B 3/4 3-7a Amendment No.

16

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