ML20070T097

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Proposed Tech Specs 3/4.3.1 Re Reactor Protection Sys instrumentation,3/4.3.6 Re Control Rod Block Instrumentation & 3/4.3.7.6 Re Source Range Monitors
ML20070T097
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 03/28/1991
From:
CENTERIOR ENERGY
To:
Shared Package
ML20070T095 List:
References
NUDOCS 9104030255
Download: ML20070T097 (8)
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Text

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PY-CEI/NRR-1284 L Attachment 2

  1. 8 '

- 3/4.3 INSTRUMENTATION S

3/4.3.1 REACTOR PROTECTION SYSTEM INSTRtMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

APPLICABILITY: As shown in Table 3.3.1-1.

ACTION:

a. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system, place

. the inoperable channel (s) an,d/or that trip system in the tripped condition

  • within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The provisions of Specification 3.0.4 are not applicable,
b. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systees, place at least one trip system ** in the tripped condition within one hour and take the ACTION required by Table 3.3.1-1.

SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor protection system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCT.IONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1.1-1.

4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip functional unit shown in Table 3.3.1-2 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one.

channel per trip system such that all channels are tested at least once every N times 18 months where N is the *,tal number of redundant channels in a specific g ]ip system.

"An inoperable channel need not be placed in the tripped condition where this-would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or the ACTION required by Table 3.3.1-1 for that Trip Function shall be taken.

    • The trip system need not be placed in the tripped condition if this would cause the Trip Function to occur. When a trip system can be placed in the tripped condition without causing the Trip Function to occur, place the trip system with the most inoperable channels in the tripped condition; if both systems have the same number of inoperable channels, place either trip system in the tripped condition.

PERRY - UNIT 1 3/4 3-1 9104030255 910328 DR ADOCK0500gO

h PY-CEI/NRR-1284 L l Attachment 2 l Page 2 of 8 Insert for page 3/4 3-1 4.3.1.4 The provisions of Specification 4.0.4 are not applicable to the Channel Functional Test and Channel Calibration surveillances for the Intermediate Range Monitors for entry into their applicable OPERATIONAL CONDITIONS (as shown in Table 4.3.1.1-1) from OPERATIONAL CONDITION 1, provided the surveillances are performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after such entry.

TABLE 4.3.1.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS S "

a CHANNEL OPERATIONAL c CHANNEL FUNCTIONAL ~ CHANNEL . CONDITIONS IN WHICH 5 CHECK TEST CALIBRATION (a) , SURVEILLANCE REQUIRED FUNCTIONAL UNIT

1. Intermediate Range Monitors:
a. Neutron Flux - High. S/U,5,(b) W R 2 S 'W R 3,4,5
b. Inoperative NA W NA 2,3,4,5
2. Average Power Range Monitor:(f)
a. Neutron Flux - High, S/U.S,(b) W SA 2 Setdown -S W SA 3, 5
b. Flow Blased Simulated Thermal Power - High S D(h) y y(d)(e), 3g(m),R I) 1
c. Neutron Flux - High S W W Id) , SA 1
d. Inoperative NA W NA 1, 2, 3, 5 "4
3. Reactor Vessel Steam Dome Pressure - High 5 M R IG) 1,2(3)* ,

i

4. Reactor Vessel Water Level -

Low, tevel 3 S M R I8) -

1, 2

5. Reactor Vessel Water Level -

High,. Level'8 5 M R I8) 1 _

6. Main Steam Line Isolation Valve - Closure NA M R 1 y>g
7. Main Steam Line Radiation - 1, 2(y) Ekh vgq High- S M R ,
8. Drywell Pressure - High S M R(9) 1, 2 E$  %-

CD 8

9. Scram Discharge Volume Water w;;

Level - High c=

a. Level Transmitter S M R(9) 1, 2, S I) r-
b. Float Switches NA M R 1, 2, 5(k)

TABLE 4.3.1.1-1-(Continued)

R REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS i

4 CHANNEL OPERATIONAL -

CHANNEL FUNCTIONAL . CHANNEL CONDITIONS FOR WHICH E FUNCTIONAL UNIT CHECK TEST CALIBRATION SURVEILLANCE REQUIRE 0

10. Turbine Stop Valve - Closure NA M A 1
11. Turbine Control Valve fast Closure Valve Trip System Oil Pressure - Low NA M R 1
12. Reactor Mode Switch Shutdown Position NA R NA 1,2,3,4,5
13. Manual Scram NA M NA 1,2,3,4,5 (a) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(b) The IRM and SRM channels.shall be determined to overlap for at least 1/2 decades during each startup after entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be determined to overlap for 1" at ey py_lpl each controlled _ shutdown hi the previous 'l days.

(c) m calitiration his shall consist.of the adjustment ogga rctG l of the APNMM:ne!:e:;;7, .; _t; -t ;F

,, t;;7: , - 15: 7 - .a:7: _

Y (d) to conf 6Tna to the power values calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER > 25% of RATED THERMAL POWER. Adjust the APRM channel if the absolute difference is greater than 2% oT RATED THERMAL POWER.

(e) This calibration shall consist of the adjustment of the APRM flow biased channel to conform to a }

calibrated flow signal.

(f) The LPRMs shall be calibrated at least once per 1000 MWD /T using the TIP system.

(g) Calibrate trip unit setpoint at least once per 31 days. .

(h) Verify measured core flow (total core flow) to be greater than or equal to (.stablished core flow at the existing loop flow (APRM % flow).

(i) This calibration shall consist of verifying the 6 1 0.6 second simulated thermal power time constant.

(j) This function is not required to be OPERABLE when the reactor pressure vessel head is removed -

per Specification.3.10.1. jll g y (k) With any control rod withdrawn. Not appitcable to control rods removed per <> g g Specification 3.9.10.1 or 3.9.10.2. . *gn (1) This function is not required to be OPERABLE when Drywell Integrity is not required. oox (m) The CHANNEL CALIBRATION shall exclude the flow reference transmitters, these transmitters shall be 'AE calibrated at least once per 18 months. -

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s PY-CE1/NRR-1284 L Attachment 2 Page 5 of 8 INSTRUMENTATION 3/4.3.6 CONTROL R00 BLOCK INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.6. The control rod block instrumentation channels shown in Table 3.3.6-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.6-2.

APPLICABILITY: As shown in Table 3.3.6-1.

ACTION:

a. With a control rod block instrumentation channel trip setpoint less conservative 2hati the value shown in the Allowable Values column of Table 3.3.6-2, declare the channel inoperable until the channel is restored te OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value,
b. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, take the ACTION required by Table 3.3.6-1.

SURVEILLANCE REOUIREMENTS

[4.3.63Each of the above required control rod block trip systems and

~1ns & Umentation channels shall'be demonstrated OPERABLE by the performance of the CHANNEL CNECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL COHOITIONS and at the frequencies shown in Table 4.3.6-1.

4.3.b.2 % pg,,ns J spcLJon A,o,4_ are, n d ,pp 6 t),, to & ,

Nnnd Vubd Test anA &nn \ 6bb 3acu&u,s Cc Re.

Lkmd' ink by Honkrs ud %e Lp Airs G rn6 b;c apkW. OPEA ATIOML OcWAmeAJS (as ske in Te e, 4.3.b-h L C9$ATiCAAL Mbmod 1, pj d k. Sm6 bus, m. p Amed w& 12.6s afbr suA eA$.

A - - -

PERRY - UNIT 1 3/4 3-55

TABLE 4.'3.6-1 CONTROL ROD-BLOCK INSTRifriENTATION SURVEILLANCE REQUIREMENTS

j3 CllANNEL OPERATIONAL CHANNEL FUNCTIONAL CONDITIONS IN WHICH

.. 3 CliANNEL . g Call 8 RATION ,)

I

, TRIP FUNCTION CHECK TEST SURVEILLANCE REQUIRED

@ 1. R00 PATIERN CONTROL SYSTEM S/D IDI .H

a. tow Power Setpoint NA SA 1, 2
b. RWL - liigh Power Setpoint NA S/U(b) ,M SA 1
2. APRM  :

l a. Flow Biased Neutron Flux - Upscale

1) LFlow Blased- NA S/U(b) ,W SA(c) 1  :

'2) liigh Flow Clamped NA S/U ,W SA IC} 1

b. Inoperative NA S/U b),W NA 1,2,5
c. Downscale NA S/U(DI,W SA -

1

d. Heutron Flux - Upscale,'Startup NA S/U I ,W SA 2, 5
3. SOURCE RANGE MONITORS

<;> a. Detector not full in NA S/U IDI NA 2"*, 5

j; b. Upscale NA ,,W W (b 2**, 5 i
c. Inoperative- NA S/Uh 2a", 5
d. Downscale' HA S/U(b)*W(M S/U , -5* R) 2**, 5
4. INIERHEDIATE RANGE MONITORS
4. Detector not full in NA S/U(b) W , NA 2, 5 fj b. Upscale . NA S/U ,W(d) R 2, 5 l,>,

ig c. Inoperative NA NA 2, 5 "

a d. Downscale NA S/U(b),W(d)

S/U ,W R 2, S l p, egg,?

$ S. SCRAM DISCilARGE' VOLUME kh g a. Water tevel - liigh NA M R 1, 2, 5* [Eh

6. REACIOR COOLANT SYSTEM RECIRCULATION FLOW "Q
a. Upscale NA' S/U(b) M , SA(c) 3 [
7. REACIOR H0DE SWITCil Sil0TDOWN '

~~

posit 1DN NA R NA 3, 4

1 PY-CEI/NRR-1284 L Attachment 2

, Page 7 of 8 INSTRUMENTATION SOURCE RANGE MONITORS LIMITING CONDITION FOR OPER;, TION 3.3.7.6 At least the following source range monitor channels shall be OPERABLE:

a. Ia OPERATIONAL CONDITION 2", three,
b. In OPERATIONAL CONDITION 3 and 4, two.

APPLICABILITY: OPERATIONAL CONDITIONS 2*, 3 and 4.

ACTION:

a. In OPERATIONAL CONDITION 2* with one of the above required source range donitor channels inoperable, restore at least 3 source range monitor channels to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or 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. In OPERATIONAL CONDITION 3 or 4 with one or more of the above required source range monitor channels inoperable, verify all insertable con- #

trol rods to be fully inserted in the core and lock the reactor mode switch in the Shutdown position within one hour.

SURVEILLANCE REQUIREMENTS 4.3.7.6 Each of the above required source range monitor channels shall be demonstrated OPERABLE by:

a. Performance of a:
1. CHANNEL CHECK at least once per:

a) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> in CONDITION 28, and b) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in CONDITION 3 or 4.

2. CHANNEL CALIBRATION ** at least once per 18 month @.
b. Performance o CHANNEL FUNCTIONAL TEST:
1. Within 2 '  : prior to moving the reactor _ node switch from the Shutdown position, &d " t" a tM a-bfta": }

Q ny Q and -

= - - -

2. At least once per 31 day ,
c. Verifying, prior to withdrawal of control rods, that the SRM count rate is at least 0.7 cps *** with the detector fully inserted.

"With IRM's on range 2 or below.

    • Neutron detectors may be excluded from CHANNEL CALIBRATION.
      • ProVided the signal-to-noise ratio is ), 2. t hMY j PERRY TUNIT 1 3/4 3-81

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l PY-CEI/NRR-1284 L  !

Attachment 2 1 Page 8 of 8 Insert for page 3/4 3-81 Note "#" for Surveillance Requirements 4.3.7.6.a.2 and 4.3.7.6.b.2:

  1. The provisions of Specification 4.0.4 are not applicable to the Channel Function Test and Channel Calibration surveillances for the Source Range Monitors fog entry into their applicable OPERATIO"AL CONDITIONS (OPERATIONAL CONDITION 2 , 3 and 4) from OPERATIONAL CONDITION 1, provided the surveillances are performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after such entry.

NJC/ CODED /4331 l

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