ML20041C989

Proposed Tech Spec Changes Re Rod Misalignment,Core Peaking Factor Limits & Associated Parameters

ML20041C989
Person / Time
Site:	Beaver Valley
Issue date:	02/23/1982
From:	DUQUESNE LIGHT CO.
To:
Shared Package
ML20041C988	List: ML20041C987 ML20041C989
References
NUDOCS 8203020720
Download: ML20041C989 (17)

Text

-. _- ._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _

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bO TABLE 2.2-1 . .

RS

• 8 . REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT TRIP SETPOINT Alt 0WABLE VALUES on "

@g g 1. Manual Reactor Trip Not Applicable Not Applicable as r-

2. Power Range, Neutron Flux Low Setpoint - 1 25% of RATED Low Setpoint - 1 26% of RATED h THERMAL POWER THERMAL POWER High Setpoint - 1 109% of RATED High Setpoint - 1 110% of RATED H THERMAL POWER THERMAL POWER

g 3. Power Range, Neutron Flux, < 5% of RATED THERMAL POWER with 1 5.5% of RATED THERMAL POWER 58 High Positive Rate a time constant > 2 seconds with a time constant > 2 seconds 8 .

4. Power Range, Neutron Flux, <5%ofRATEDTHERMklPOWERwith < 5.5%- of RATED THERMAL POWER E!

g High Negative Rate a time constant 1 2 seconds with a time constant 1 2 seconds k ';* 5. Intermediate Range, Neutron 1 25% of RATED THERMAL POWER 1 30% of RATED THERMAL POWER 5

• Flux

6. Source Range, Neutron Flux 101counts 5 per second 1 1 3 x 105counts per second

7. Overtemperature AT See Note 1 See Note 3

8. Overpower AT See Note 2 See Note 3

9. Pressurizer Pressure--Low 1 1945 psig g 1935 psig

10. Pressurizer Pressure--High 1 2385 psig i 2395 psig

11. Pressurizer Water Level--High 1 92% of instrument span 1 93% of instrument span

12. Loss of Flow 1 90% of design flow 1 89% of design flow per loop per loop

• Design flow is 88,500 gpm per loop.

O

i TABLE 2.2-1 (Continued) h REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS

i

,

• NOTATION (Continued)

N j p Operation with 3 Loops Operation with 2 Loops Operation with 2 Loops j '2

. (noloopsisolated) (1loopisolated)

$ Ky = 1.18 K j = 0.99 K j = 1.1 i 5 K = 0.01655 K = 0.01655 K = 0.01665

] 2 2 2

g K = 0.000801 K = 0.000801 K = 0.00%01 3 3 3 e

O m and f (AI) is a function of the indicated difference between top and bottom detectors

@a e of the power-range nuclear ton chambers; with gains to be selected based on measured instrument response during plant startup tests such that:

g

$ (1) between -23 percent and + 11 percent, f (AI) = 0 l forq$q-qIndq (wher are percent RATED THERMAL POWER in the top and bottom halvesofthecNrerespectivel,andqt*9 b is total THERMAL POWER in percent of RATED THERMAL POWER (ii) for each percent that the magattude of (qi - qh) exceeds -23 percent, the AT trip setpoint shall be automaticalTy reauced by 1.54 percent of l

its value at RATED THERMAL POWER.

(iii) for each percent that the magnitude of (q -q exceeds + 11 percent. l theATtripsetpointshallbeautomaticalfyrebu)cedby1.91percentof its value at RATED TilERMAL POWER.

I I

I ,

1 SAFETY L1MITS

\

BASES andThe curves are based on an enthalpy hot channel factor, F a reference cosine with a peak of 1.55 for axial pe. Anpower sha$

3 allowance is included for an increase in F ggat reduced power based on the expression:

N F3H = 1.55 [1 + 0.3 (1-P)] l where P is the fraction of RATED THERMAL POWER These limiting heat flux conditions are higher than those calculated for the range of all control rods fully withdrawn to the maximum allowable control rod insertion assuming the axial power imbalance is within the limits of the f(AI) function of the Overtemperature trip. When the axial power imbalance is not within the tolerance, the axial power imbalance effect on the Overtemperature AT trip will reduce the setpoint to provide protection consistent with core safety limits.

. 2.1. 2 REACTOR COOLANT SYSTEM PRESSURE

! The restriction of this Safety Limit protects the integrity of the Reactor Coolant System from overpressurization and thereby prevents the release of radionuclides contained in the reactor coolant from reaching the containment atmosphere. ,

The reactor pressure vessel and pressurizer are designed to Section III of the ASME Code for Nuclear Power Plant which permits a maximum transient pressure of 110% (2735 psig) of design pressure. The Reactor Coolant System piping and fittings are designed to ANSI B 31.1 and the valves are designed to ASA 16.5 which permit a maximum transient pressure of 120% (2985') psig of component design pressure. The Safety Limit of 2735 psig is therefore consistent with the design criteria and associated code requirements.

The entire Reactor Coolant System is hydrotested at 3107 psig to demonstrate integrity prior to initial operation.

l BEAVER VALLEY - UNIT 1 B 2-2 PROPOSED WORDING l

l REACTIVTTY CONTROL 5'tSTEMS 3 /4.1. 3 MOVA8LE CONTROL ASSEMBLIES GROUP HEIGHT t LIMITING CONDITION FOR OPERATION 3.1.3.1 All full length (shutdown and control) rods which are inserted in the core shall be OPERABLE and positioned within + 16 steps (determined in accordance with Specification 3.1.3.2 of their group step counter demand position.

APPLICABILITY: MODES 1* and 2*

ACTION:

a. With one or more full length rods inoperable due to being immovable as a result of excessive friction or mechanical i

interference or kncwn to be untrippable, detemine that the l SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied within I hour and be in HOT STAN05Y within ,6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. With more than one full length red 150PERABLE or indicated to be misaligned frem any other red in its grcup by more than

+ 16 steps (deter nined in accordance with Specificatien 3.1.3.2),

Fe in HOT STAN05Y within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

c. With one full length rod inoperable or indicated to be misaligned t

from its grcup step.ccunter demand height by more than i16 steps l (detennined in ac'cordance OPERATION with S that may continue provided'pecification within one hour either: 3.1.3.2), PO j

1. The rod is restored to CPERAELE st'atus within the above siignment requirements, or

2. The rod is declared inoperable and-the SHUTDOWN PARGIN require. ment of Specification 3.1.1.1 is satisfied.

POWER OPERATION may then continue previded that:

a) An analysis of the potential ejected rod worth is performed wf thin 3 days and the red worth is determined to be < 0.95% Ak at zero pcuer and

< 0.20% Ak at RATI.D THERMAL POWER for the Femainder of the fuel cycie, and b) The SHUTUOWN MARGIN requirement of ,,,,ecification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and

• See special Tese Exceptions 3.10.2 and 3.10.4 l

BEAVER VALLEY - UNIT I 3/4 I-I8 PROPO. SED WORDING

REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) c) The HERMAL POWER level is reduced to < 75% of RATED THERMAL PouER within cne hour and withT'n the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the high neutron flux trip setpoint is reduced to < 85% of RATED THERMAL POWER, or i d) The remainder of the rods in the group with the l inoperable red are aligned to within + 16 steps of the inoperable red within one hour whI'le maintaining the red sequence and insertion limits of Figures 3.1-1 and 3.1-2; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.5 during subsequent operation.

SURVEILLANCE RECUIREMENTS 4.1.3.1.1 The position of each full length red shall be determined to be within the group. demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify'the group positions

( at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4.1.3.1.2 Each full length rod not fully inserted shall be determined l

to be OPERABLE by movement of at least 10 steps in any one direction at l

1 east once per 31 days.

l r

BEAVER VALLEY - UNIT 1 3/4 1-19

' PROPOSED WORDING

l REACTiVKTY CONTROL SYST&.5 POSITION INDICATOR CHANNELS LIMITING CCNDITION FOR OPERATION 3.1.3.2 For Cycle 2 operation, all shutdown and control red position indicator channels and the demand position indicatien system shall be OPERABLE and capable of determining the control red positions within

+ 16 steps by direct analog indication or as a backup by measurement i oIf channel detector primary voltages. If a red position indicator analog channel indicates 16 steps or more deviation frem the grcup demand I indicator, rod positions for the affected reds shall be determined by measuring detector primary voltages, as follows:

a. immediately,

b. if associated rods move greater than 8 steps (greater than 16 l steps if all rods in the grcup have been determined to be within 8 steps of the group demand indicator by primary voltage measurs- l ments within the previous 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />),

c. at 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> intervals if the affected red (s) .are not fully inserted or fully withdrawn,

d. at 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> intervals if the affected red (s) are fully inserted or fully withdrawn.

When the red position indicator channel is INOPERABLE, the position of not more than three centrol reds per bank which are not fully inserted or fully withdrawn may be determined by use of the detector primary voltage measurements.-

APPLICABILITY: Modes 1 and 2*

ACTION:

a. If greater than 3 red position indicators per bank, for banks not fully withdrawn or fully inserted, are INOPERABLE, then i declare the rod position indicator system to be INOPERABLE i and be in HOT STANCSY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after the allowed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> I stabilization period and in COLD SHUTDOWN in the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. Submit a Special Report to the NRC by telephone and in writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or by the close of the next business day, whichever is later. Restore all affected Rod Position Indicators to OPERABLE status prior to entry to Mode 2.

b. If the position of a maximum of one red cannot be determined

by either the direct reading of the red position indicators or by reading primary detector voltage measurements, either:

1. Cetermine the position of the non-indicating red indirectly I by the movable incore detectors immediately and at least once per 8 .heurs and immediately after any motion of the non-indicating red which exceeds 32 steps in one directicn l since the last determination of the red's position, or

2. Reduce THERMAL PCWER TO < 50% of RATED THERNAL F0WER within 8 hcurs.

I BEAVER VALLEY - UNIT 1 3/4 1-20 PROPOSED WORDING

. . REACTIVITY CONTROL SYSTEMS , ,

ACTION: (Continued)

c. With a maximum of one demand position indicator per bank inoperable, either:

1. Verify that all rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of 16 steps of each other immediately after rod motion greater than 8 steps (greater than 16 steps if all rods in the group have been determined to be within 8 steps of the group demand indicator by voltage measurements within the previous 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or

2. Reduce THERMAL POWER TO < S0% of RATED THEF#AL POWER

, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

d. If the position of more than one rod cannot be determined by either the direct reading of the red position indicators or by reading primary detector voltage measurements, then Specification 3.0.3 is applicable.

SURVEILLANCE REQUIREMENTS I

4.1.3.2 Each rod position indicator channel shall be detemined to be OPERABLE by verifying the demand position indication system and.the red position indicator channels agree within 16 steps at least once per 12 l hours (except during time intervals when the Red Position Deviation

' Monitor is INOPERABLE or is in a continuous state of alarm), then compare the demand position indication system and the rod position indicator channels at approximately 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> intervals, as follows:

a. If an individual rod position indicator analog channel does not

! settle to within + 16 steps within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, then declare that l channel IN0pERABLT.

l l i

l b. For any INOPERABLE channel, no repairs or adjustments shall

be permitted without being followed immediately by a full i range calibration.

I

• For core PHTSICS TESTING in Mcde 2, primary detector voltage measurements may be used to determine the position of rods in shutdown banks A and B

! and control banks A and B for the purpose of satisfying Specification 3.1.3.2. During Mode 2 operations, rod position indicators for shutdewn banks A and B and control banks A and 8 may deviate from the group demand indicators by greater than + 16 steps during reactor startup

. l and chutdown operations, while red:; are being withdrawn or inserted.

l If the red position indicators for shutdown banks A and B and control banks A and B deviate by greater than + 16 steps from the group demand I indicator, rod withdrawal or insertion hay continue until the desired group height is achieved.

1 BEAYER VALLEY - UNIT 1 3/4 1-2CA .

PROPOSED WORDING

' POWER DISTRIBUTION LIMITS HEAT FLUX HOT CHANNEL FACTOR-F O III LIMITING CONDITION FOR OPERATION 3.2.2 F q(Z) shall be limited by the following relationships:

Fq (Z) 1 p [K(Z)3 for P > 0.5 Fq (Z) 1[( 4.64)] [K(Z)] for P 10.5 THERMAL POWER where P = W ED THE m power and K(I) is the function cbtained frem Figure 3.2-2 or Figure 3.2-3 for a given core height location.

APPLICABILITY: MODE 1 ,

ACTION:

With Fq (I) exceeding its limit:

a. Reduce THERMAL POWER at least 1% for each 11 F (I) exceeds the limit within 15 minutes and similiarly reduce 9he Power Range Neutron Flux-High Trip Setpoints within the next 4 hcurs; POWER OPERATION may ;:roceed for up to a total of 72 hcurs; subsequent POWER OPERATION may proceed provided the .0verpcwer AT Trip Setpoints have been reduced at least 1% for each 1%

Fn(Z) exceeds the limit. The overpewer AT Trip setpoint rlduction shall be perfor.::ed with the reactor subcritcal,

b. Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; THERMAL POWER may then be increased provided F q (Z) is de=enstrated through inc:re mapptng to be within its limit.

BEAVER VALLEY - UNIT 1 3/4 2-5 PROPOSED WORDING

1

~ POWER DISTRIBUTION LIMITS j

SURVEILLANCE REOUIREMENTS

4.2.2.1 The provisions of Specification 4.0.4 are not applicable.

i 4.2.2.2 limit by: F*Y shall be eval.uated to determine if F (Z) is within its 0

a. Using the movable incore detectors to obtain a power distribu-tion map at any THERMAL POWER greater than 5% of RATED THERMAL POWER.

l

b. Increasing the measured F e mponent of the power distribution map by 3% to account for Enufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties.

C

c. Comparing the F xy computed (Fx ) obtained in b, above to:

P

1. The Fxy limits for RATED THERMAL POWER (Ffy ) for the appropriate measured core planes given in e and f below,

.. and

2. The relationship: .

[1+0.} (1-P)]

Fh=F x

l where F*7 is the limit for fractional RTPTHERMAL POWER and P is operation expressed as a function of Fxy the fraction of RATED THERMAL POWER at which Fy was measured.

d. Remeasuring F according to the following schedule:

xy

1. When F C is greater than the F limit for the appropriate x

measured core plane but less than the F relationship ,

additional power distribution maps shall be taken and FfcomparedtoF and F  :

x a) Either within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding by 20% of

! RATED THERMAL POWER or greater, the THERMAL POWER at which Fx was last determined, or C

BEAVER VALLEY - UNIT l 3/4 2-6 Amendment No. 2 PROPOSED WORDING

POWER DISTRTBUTION LIMITS

• o SURVEILLANCE REQUIREMENTS (Continued)

~

b) At least once per 31 EFPD, whichever occurs first.

2. When the F is less than or equal to the F limit for theappropYlatemeasuredcoreplane,adgit1Ea1 power distribution maps shall be taken and F compared to F RTP and F L at least once per 31 EFP E XY XY

e. The F limit for Rated Ther=al Power (FX7 ) shall be provided XY for all core planes containing bank "D" control rods and all unrodded core planes in a Radial Peaking Factor L1=1t Report per specification 6.9.1.10.

f. The F limits of e, above, are not applicable in the following core plane regions as =easured in percent of core height from the bottom of the fuel:

1. Lower core region from 0 to 15%, inclusive.

2. Upper core region from 85 to 100% inclusive.

3. Grid plane regions at 17.8 I 2*., 32.1 1 2%,

46.4 t 2%, 60.6 t 2% and 74.9 2*, inclusive

4. Core plane regions within

• 2" of core height (I 2.88 inches) about the bank demand position of the bank "D" centrol rods.

C '

g. With F exceeding F ", the effects of F on F XY X7 X7 Q (Z) shall be evaluated to determine if F (Z) is within its limit.

4.2.2.3 When F (Z) is measured pursuant to Specification 4.10.2.2, an over-all measured F (Z) shall be obtained from a power distribution map and j increased by 3% to account for manufacturing tolerances and further increased by 5% to account for measurement uncertainty.

l BEAVER V ALLEY- U NIT 1 3/4 2-6a l

PROPOSED WORDING

K(Z) - NORMALI2ED FQ(Z)

AS A FUNCTION OF CORE HEIGHT N-LOOP BEAVER VALLEY - UNIT 1

2;

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l l BEAVER VALLEY - UNIT 1 3/4 2-7 l

PROPOSED WORDING

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AS A FUNCTION OF CORE HEIGHT N-1 LOOP BEAVER VALLEY - UNIT 1

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Figure 3.2-3 BEAVER VALLEY - UNIT 1 3/4 2-7a PROPOSED WORDING

POWER DISTRIBUTION LIMITS N

m NUCLEAR ENTHALPY HOT CHANNEL FACTOR - T'AH LIMITING CONDITION FOR OPERATIOV N

3.2.3 FbH shall be li=ited by the following relationship:

F3g 51.55 [1 + 0.3 (1-P)] [1-R3P(3U))

Where P = THERMAL POWER PATED THERMAL POWER RSP (BU) = Rod Bow Penalty as a function of region average burnup as shown in Figure 3.2-4, where a region is defined as those asse=blies with the same loading date (reloads) or enrich =ent (first cores).

APPLICABILITY: MODE 1 ACTION:

N With Foh, exceeding its 11=1::

a. Reduce HERMAL POWER to less than 50% of RATED THERv.lL POWER wi:hin 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flux-High Trip Se: points to 5 55% of RATED THERMAL POWER within the nex: 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, e

b. De=onstrate thru in-core mapping that 7"H is within its 11=it within A

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding the 11=1; or reduce THEFyll POWER to less than 5% of RATED THERMAL POWER within the nex: 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, and

c. Identify and correct the cause of the out of 11=1; condition prior to increasing TEER. val POWER; subsequent POWER OPERATION =ay proceed N

provided that F is de=onstrated through in-core capping to be with-H in its li=it at a no inal 50% of RATED THERMAL POWER prior to exceeding this THERMAL POWER, at a nominal 75% of RATED THEPEAL POWER prior to exceeding this THERMAL power and within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after attaining 95%.or greater RATED THERMAL POWER.

SEAVER V ALL EY- U NIT 1 3/4 2-8 PROPOSED WORDING

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POWER DISTRI3UTION LIMITS m

BASES An evaluation of DN3 and test data fro = experiments of fuel rod bowing in subchannels containing th1=ble cells has identified that it is appropriate to inpose a penalty factor to the accident analyses DNBR results. Accordingly, a thi=ble cell rod bow penalty as a function of f uel burnup, is applied to the N

=ecsured values of the enthalpy rise hot channelfactor,FbH. Additional in-plant operrtional data and DN3 tests designed to quantify the effects of rod bow have provided a basis for reducing the penalty applied to the enthalpy rise hot channel factor to account for rod bow effects. The necessary penalty is applied as a function of fuel burnup (See Figure 3.2-3).

l The radial peaking factor Fg (~) is =easured periodically to provide assurance ,

that the hot channel factor, FQ (Z), re=ains within its limit. The F li=it for xv Rated Ther=al Power (F f ) as provided in the Radial Peaking Factor Li=1: Report per specification 6.9.1".10 was determined fro = expected power control =aneuvers I over the full range of burnup conditions in the core.

3/4.2.4 OUADRANT POWER TII.T RATIO The quadrant power til: ratio licit assures that the radial power distribution satisfies the design values used in the power capability analysis. Radial power distribution =easure=ents are =ade during startup testing and periodically during power operation.

The li 1t of 1.02 at which corrective action is required provides DN3 and linear heat generation rate protection wi:h x-y plane power tilts.

The two hour time allowance for operation with a til: condition greater than 1.02 but less than 1.09 is provided to allow identification and correction of a dropped or misa11gned rod. In the event such action does not correct the tilt the =argin for uncertainty on F is reinstated by reducing the =aximu= allowed, power by 3 percent for each percent of tilt in excess of 1.0.

BEAVER V ALLEY- U NIT 1 33/4 2-5 PROPOSED WORDING

. ?. . .

ADMINISTRATIVE CONTROLS

i. Performance of stractures, systems, or components that , requires remedial action or corrective measures to prevent operation in a manner less conservative than that assumed in the accident analyses in the safety analysis report or technical specifications bases; or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.

THIRTY-DAY WRITTEN REPORT 6.9.1.9 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within 30 days of occurrence of the event.

The written report shall include, as a minimum, a completed copy of a licensee event report form. Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explaqation of the circumstances surrounding the event.

a. Reactor protection system of engineered safety feature instrument settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems,

b. Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation.

c. Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy pro-vided in reactor protection systems or engineered safety feature systems.

d. Abnormal degradation of systems other than those specified in 6.9.1.8.c above, designed to contain radioactive material resulting from the fission process.

RADIAL PEAKING FACTOR LIMIT REPORT 6.9.1.10 The Fxy limit for Rated Thermal Power (F shall be provided to the Director of the Regional Office of Inspection and Enforcement, with a copy to the Director, Nuclear Reactor Regulation , Attention Chief of the Core Performance Branch, U. S. Nuclear Regulatory Commission, Washington, DC 20555 for all core planes containing bank "D" control rods and all unrodded core planes at least 60 days prior to cycle initial criticality. In the event that the limit would be submitted at some other time during core life, it will be submitted 60 days BEAVER V ALLE Y- U NIT 1 6-16 PROPOSED WORDING i

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ADMINISTRATIVE CONTROLS prior to the date the limit would become effective unless otherwise exempted by the Commission.

RTP Any information needed to support F will be by request from the NRC and need not be included in this report.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted tc the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a. Inservice Inspection Program Reviews, Specifications 4.4.10.1 and 4.4.10.2.

b. ECCS Actuation, Specifications 3.5.2 and 3.5.3.

c. Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.

d. Inoperable Meteorological Monitoring Instrumentation, Specifi-cation 3.3.3.4.

e. Seismic event analysis, Specification 4.3.3.3.2.

f. Sealed source leakage in excess of limits, Specification 4.7.9.1.3.

g. Fire Detection Instrumentation, Specification 3.3.3.6.

h. Fire Suppression Systems, Specification 3.7.14.1, 3.7.14.2, and 3.7.14.3.

6.10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:

a. Records and logs of facility operation covering time interval at each power level,

b. Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.

c. All REPORTABLE OCCURRENCES submitted to the Commission.

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.

BEAVER V ALL EY- U NIT 1 6-17 PROPOSED WORDING