ML20214Q607

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Safety Evaluation Supporting Util 851017 Proposed Tech Spec Changes Re Reactor Trip Sys Instrumentation & Surveillance in Response to Generic Ltr 83-28,Item 4.3,under Guidance of Generic Ltr 85-09
ML20214Q607
Person / Time
Site: 05000000, Salem
Issue date: 06/06/1986
From:
NRC
To:
Shared Package
ML20213E339 List:
References
FOIA-87-152 GL-83-28, GL-85-09, GL-85-9, NUDOCS 8706050089
Download: ML20214Q607 (11)
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Text

{{#Wiki_filter:n SAFETY EVALUATION REPORT TECHNICAL SPECIFICATION CHANGE 5 (MPA B-90) 5ALEM GENERATING STATION, UNITS 1,2 INTRODUCTION By letter dated October 17, 1985, Public Service Electric and Gas Company sub-mitted proposed changes to the Salem Technical Specifications pertaining to Reactor Trip System Instrumentation and Surveillance that were responsive to Item 4.3 of Generic Letter 83-28. Guidance for these changes was provided by Generic Letter 85-09 (MPA B-90). Generic Letter 85-09 concluded that Technical Specification changes should be proposed by licensees to explicitly require in-dependent testing of the undervoltage and shunt trip attachments of the reactor trip breakers during power operation, testing of bypass breakers prior to use, and independent testing of the control room manual switch contacts and wiring during each refueling outage. EVALUATION The licensee's proposed Technical Specification changes are consistent with those of Generic Letter 85-09 except as indicated below. No changes have been proposed for Functional Units 21 (Reactor Trip Breaker) and 22 (Automatic Trip Logic) of Table 3.3-1 (ReactorTripSystemInstrumentation). For each of these func-tional units, Modes 3, 4 and 5 should be separated from Modes I and 2, and an action similar to Action 13 of Generic Letter h 85-09 should then be applied to Modes 3, 4, and 5 (1)

Also, og n, in additinn to the pt ?sently indicated Action 1 for Modes 1 and 2 o

"di of Functional Unit 21, the licensee should add an action *similar 8+ o'p0S g to Action 14 of Generic Letter 85-09. 4 t gtu Sn.3 (1) The

  • means that the action applies with the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

We believe the above changes for Modes 3, 4 and 5 are appropriate because Action 1 requires a change to Hot Standby within 6 hours if the number of oper-able channels are one less than the minimum required. Such an action is not appropriate for Modes 3, 4 and 5, and in fact would be-in the wrong direction for Modes 4 and 5, The above change to Modes 1 and 2 is needed to provide for the situation when only one of the diverse trip features of a reactor trip breaker is inoperable. For Table 4.3-1, we find the licensee's proposed changes consistent with, and more exact than, those of Generic Letter 85-09. These proposed changes are therefore acceptable. CONCLUSION We find the Technical Specification changes proposed by Public Service Electric and Gas Company for the Salem Generating Station, Units 1 and 2, to be accept-able except that a separate action statement similar to Action 13 of Generic Letter 85-09 should apply to modes other than Modes 1 and 2 of Functional Units 21 and 22 of Table 3.3-1. Also, for Modes 1 and 2 of Functional Unit 21, an action similar to Action 14 of Generic Letter 85-09 should be added. The licensee should submit for staff review proposed Technical Specification changes for these functional units that are consistent with Generic Letter 85-09.

ENCLU:,ddt. l ICSB SA!P litPUT Salem Generating Station, Units 1 and 2 Technical Specification Changes (MPA B-90) ptAny.

SUBJECT:

PERFORilANCE ggggs EVALUATION CATEGORY CRITERIA No basis for assessment. N/A Management Involvement While approach was sound, it did not conpletely address the issues. 2 Appro:ch to Resolution of - Technical Issues Although not coupletely responsive, submittal was accurate and timely. Responsiveness 2 No basis for assessment. 1 N/A Enforcement llist ry "I^ Repcrtable Events No basis for assessm<nt. T N/A 1 ;4 fug

  • ~ ~ '

No basis for assessment. N/A Training G

~ o TABLE 4.3-1 (Cont.inued) ~ } h REACTOR 1 RIP SYSTEM INSTRtKNI AT10rl StRVEILLNCE REWlREENTS [ CHMKl. MMIES IN lHICM CHANEL FIETIONM. SERVE!LIACE I FUNCTIONAL UNIT CHECK CALIBRATION TEST REWIRED l l l

13. Inss of Flow - Tuo loops S

R NA. 1 .l j

14. Steam Generator lhter level-- tow-law S

R M 1, 2

15. Steam /Feedseter Flow Mismatch & low l

Steam Generator 14ter level S R M 1, 2 1

16. Underal$ age -Reactor Coolant Fusps NA.

R M 1 ,,1

17. Underfrequency - Reactor Coolant Fbsps NA.

R M 1

18. Turbine Trip j
a. Low Autostop 011 kessure NA.

NA. S/U(1) 1, 2

b. Turbine Stop Valve Closure NA.

NA. S/U(1) 1, 2 ~

19. Safety injection input from SSPS NA.

NA. M(4) 1, 2 i l

20. Reactor Coolant Pump Breaker Pbsition Trip NA.

NA. R NA. - 21. Reactor Trip Breaker NA. N.A. S/U(10) 11 ) R( 4 1, 2 and *

22. Automatic Trip togic NA.

NA. M(5) 1 f'a'nd

  • i l

g)h)

v ~ d TABLE 4.3-1 (Continued) NOTATION With the. reactor trip system breakers closed and the control rod drive system capable :,f rod withdrawal. If not performed in previous 7 days. k (1) Heat balance only, above 15% of RATED THERMAL P0iER. (2) (3) - Cospare incore to excore axial offset above 15% of RATED THERMAL POER. Recalibrate if absolute difference > 3 percent. (4) - Manual SSPS functional input check every 18 sonths. (5) Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST 8 ASIS. (6) Neutron detectors say be excluded frosi CHANNEL CALIBRATION. (7) Below P-6 (Block of Source Range Reactor Trip) setpoint. (8) Logic only, if ret performed in previous 92 days. (9) If not performee in the previous 24 hours, conduct a functional test of the Manual Reactor Trip Switches to verify the Manual Reactor Trip Switch and the independent operation of the U.V. and snunt trip wiring. (10) If not performed in the previous 24 hours, conduct a functional test of: Reactor Trip Breaker independent operation of U.V. and Shunt Trip (via SSPS) .. Reactor Trip Breaker Shunt Trip (via manual pushbutton controls) (11) Perform a functional test of: Reactor Trip Breaker independent operation of U.V. Trip and Shunt i Trip (via SSPS) and conduct response time testing of U.V. and Shunt Trip /8reakers (event recorders) Reactor Trip Breaker Shunt Trip (via manual pushbutton controls) (12) Perform periodic maintenance on Reactor Trip Breakers and Reactor Trip Sypass Breakers semiannually as follows: a. response time testing (3 times) (visicorder) trend dati i b. trip bar lift force masurements c. U.V. output force measurement 1 d. dropout witage check e. servicing / lubrication / adjustments (See Table 3.3-1 tbtation H#) f. repeat testing stars (a-d) following any necessary actions at step (e) SALEM - UNIT 1 3/4 3-13

TABLE 4.3-1 (Continued) (13) Verify operation of Bypass Breakers Shunt Trip function from local pushbutton while breaker is in the test position prior to placing breaker in service. g (14) Perform a functional test of the Bypass Breakers U.V. Attachment via the SSPS. i SALEM - UNIT 1 3/4 3-13a .,-.,,_,--,-.--..-n--

f 7 M 9 TABLE 3.3-1 (Continued) s c.. ~ O. REACT 0il TRIP SYSTEM INSTRUMENTATION w m MINIMUM TOTAL NO.* CHANNELS CllANNELS APPLICABLE FUNCTIONAL UNIT OF CllANNELS TO TRIP OPERABLE. MODES ACTION

18. Turbine Trip a.

Low Autostop Oil Pressure 3 2 2 1 7; h. Turbine Stop Valve Closure 4 4 4 1 7p 19. Safety injection input from SSPS 2 1 2 1,2 1 u = I

20. Reactor Coolant Pump Breaker wI.

Position Trip a. Above P-8 1/ breaker 1 1/ breaker 1 10 b. Above P-7 1/ breaker 2 1/ breaker 1 11 i per oper-F ating loop - " ~ ~ ~ t e I

21. Reactor Trip Breakers 2

1 2 1, 2 and'* 57## 1

22. Automatic Trip Logic 2

1 2 1, 2 and

  • 1 o

e 0 ) e 9 6 e

?j p - t TABLE 3.3-1 (Continued) 1 TABLE NOTATION

  • With the reactor trip system breakers in the closed pcsition and the control rod drive system capable of rod withdrawal.
    • The channel (s) associated with the protective functions derived from the oct of service Reactor Coolant loop shall be placed in the tripped ccndt tion.
  1. The provisions of Specification 3.0.4 are not applicable, i
    1. High voltage to detector may be de-energized above P-6.
      1. If ACTION Statement 1 is entered due to the results of maintenance testing on Reactor Trip Breakers (RTB) or Reactor Trip Bypass Breakers (RT88) exceeding any procedural acceptance criteria, or RTB/RTB8 trip forces exceeding the recommended upper limit, innediate NRC notification [within 1 hour and prior to any repair or adjustment to the affected breaker (s)] is required in accordance with Specification 6.9.2 ACTION STATEMENTS ACTION 1 - With the number of channels'0PERABLE one less tha'n required by the

( Minimum Channels OPERABLE requirement, be in HOT STAN08Y within 6 hours; however, one channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.1.1 provided the other char.nel is OPERABLE. ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied: a. The inoperable channel is placed in the tripped condition within I hour. b. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 2 hours for surveillance testing per Specification 4.3.1.1. r Either, THERMAL POWER is restricted to less than or equal to 75". c. of RATED THERMAL and the Power Range, Neutron Flux trip setpoint is reduced to less than or equal to 85". of RATED THERMAL POWER i within 4 hours; or, the QUADRANT POWER TILT RATIO is monitored at l least once per 12 hours. s d. The QUADRANT POWER TILT RATIO, as indicated by the r.emaining l three detectors, is verified consistent'with the normalized symmetric power distribution obtained by using the movable in-core detectors in the four pairs of symmetric thimble locations at least once per 12 hours when THERMAL POWER is greater than 75% of RATED THERMAL POWER. 1 SALEM - UNIT 2 3/4 3-5 Amendment No. 28 .s -,m-

~ ~ j p.- m t 2 ' y e TABLE 4.3-1(Continued) ,m 2 x I I REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS e i =' CHANNEL MOUES IN WHICH-ro CHANNEL FUNCTIONAL SURVEILLANCE 1 FUNCTIONAL l'itlT CllECX CALIBRATION TEST REQUIRED

13. Loss of Flow

__Two Loops S R N.A. 1

14. Steam Generator Water Level--

Low-Low S R M 1, 2

15. Steam /Feedwater Flow Mismatch &

Low Steam Generator Water Level S R H 1, 2

16. Undervoltage - Reactor Coolant Pumps N.A.

R* M 1 l s

17. Underfrequency'O Pr rar Coolant

_Y' Pumps N.A. R H 1 to i-

18. Turbine Trip a.

Low Autostop 011 Pressure N.A. N.A. S/U(1) N.A. b. Turbine Stop Valve Closure N.A. N.A. S/U(1) N.A. v 19. Safety injection input from SSPS N.A. N.A. M(4) 1, 2 * =

20. Reactor Coolant Pump Breaker

!k Position Trip N.A. R S/U(8) 1 i S L2 21. Reactor Trip Breaker N.A. N.A. S/U(10),M(ll)

1. 2 and *

]P and SA(12) to A. {"

22. Automatic Trip Logic N.A.

N.A. N(5) 1, 2 and

  • 1 i

i a b

] l i

.t,

i TABLE 4.3-1 (Continued) NOTATION { With the reactor trip system breakers closed and the control rod drive = system capable of rod withdrawal. ~ If not performed in previ.ous 7 days. (1) Heat balance only, above'15% of RATED THERMAL POWER. { (2) (3) Compare incere to excore axial offset above 15% of RATED THERMAL POWER. Recalibrate if absolute difference] 3 percent. ,e-(4) Manual SSPS functional input check every 18 months. o (5) Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST 8 ASIS. (6) Neutron detectors may be excluded from CHANNEL CALIBRATION. (7) Below P-6 (Block of Source Range Reactor Trip) setpoint. (8) Deleted If not p'erformed in the previous 24 hours, conduct a functional test of (- (9) the Manual Reactor Trip Switches (using voltmeters). (10) - If not performed in the previous 24 hours, conduct a functional tes_t of: a Reactor Trip Breaker UV Trip (via SSPS) ~ ~ Reactor Trip 8reaker Shunt Trip (via manual pushbutton controls) e (11)- Perform a functional test of: e Reactor Trip Breaker UV Trip (via SSPS) and conduct response time testing of UV/8reakers (event recorders) Reactor Trip Breaker Shunt Trip (via manual pushbutton con'trols) e ' erform periodic maintenance on Reactor Trip Breakers and Reactor Trip (12)- P Bypass Breakers semiannually as follows: a. response time testing, (3 times) (visicorder) trend data b. trip bar lift force measurements c. UV output force measurement d. dropout voltage check e. servicing / lubrication / adjustments (See Table 3.3-1 Notatjon #ff) f. repitat testing steps (a-d) following any necessary actionsr-at step (e) k SALEM - UNIT 2 3/4 3-13 Amendment No. 36 _,m-.y***.muy - e _sm

=

~ TABLE 3.3-1 (Continued) ACTION STATEMENTS (Continuedl

ble, With a channel associated with an operating loop inopera ithin 2 hours restore the inoperable channel to OPERABLE status w ACTION 9 One or be in at least HOT STANDBY within the next 6 d for i tion 4.3.1.1.

up to 2 hours for surveillance testing per Specif ca lessthantheMinimuE l' A'CTION 10 - With the number of OPERABLE Channels oneC THERMAL POWER to to OPERABLE status within 2 hours or reduce it below the P-8 (Power Range Neutron Flux Interlock) setpo within the next$2 hours. continue pursuant to ACTION 11, ~~ h the Minimum ACTION 11 - With the number of OPERABLE Channels dd dition the inoperable channel is placed in the tripped con within 1 hour. less than the Minimum ACTION 12 - With the number of OPERABLE channels oneC within 6 hours; however, one channel may be2 hou provided the other channel is OPERABLE. less than the Minimum ACTION 13 - With the number of OPERABLE channels one l Channels OPERA 3tE requirement, restore the inoperable ch t trip to OPEARABLE status within 48 hours or open the reac or ~ breakers within the next hour. h t With one of the diverse trip features (undervoltage or s UNAB trip attachment) inoperable, restore it to OPER t ACTION 12. ACTION 14 The breaker shall not be bypassed while one of the diverse ired for trip features is inoperable except for the time requ OPERABLE status. perfonning maintenance to restore the breaker to A GL TE ~ Q 7 ' I ? ' % *%W **:' = s.s -,;y, Mf&m.Qe uc' ?.s! 3/4 3 9 J; 4 y-STS f,6 J ~ s '-gw g -' '"4 T-'8W $' M' 4 +9'+'"+- W- = '}}

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