Text

Proposed Tech Specs 3.3.3.7 Action 3 Re Post Accident Monitoring Sys
	ML18096B303
Person / Time
Site:	Salem
Issue date:	02/23/1993
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML18096B302	List: ML18096B301; ML18096B303;
References
	NUDOCS 9303020469
	Download: ML18096B303 (8)
	v • d • e

ATrACBMEN'r 2

!ABLE 3.3-11 (continue*

TABLE NOTATION ACTION 1 With the number of OPERABLE accident monitoring channels less than the RequirPd Number of Ch2nnels shown in Table 3.3-11, ~=store the inoperable channel(s) to. OPERABLE status within 7 days, or be in HOT SHUTDO'WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 2 With the number of OPERABLE accident monitoring channels less than the Minimum Number. of* Channels shown in Table 3.3-11, restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 3 With the number of OPERABLE channels one less than the Requiredl Number of Channels shown in Table 3.3-11, operation may procee~

provided that the Boric Acid Tank associated with the remaining OPERABLE channel satisfies all requirements of Specification 3.1.2.6.a., otherwise comply with the requirements of 3.1.2.6 action a.

ACTION 4 With: the; number o*f OPERABLE channels one less than the Required Number of Channels shown in Table 3.3~11, operations may proceed provided that an OPERABLE Steam Generator Wide Range Level channel is available as an alternate means of indication for thE.

Steam Generator with no OPERABLE Auxiliary Feedwater Flow Rate Channel.

ACTION 5 With the number of OPERABLE channels less than the Required Number of Channels show in Table 3.3-11, operation may proceed provided that Steam Tables are available in the Control Room and the following Required Channels shown in Table 3.3-11 are OPERABLE to provide an alternate means of calculating Reactor Coolant System subcooling margin:

a.

Reactor Coolant Outlet Temperature - THOT (Wide Range)

b.

Reactor Coolant Pressure (Wide Range)

SALEM - UNIT 2 3/4 3-Slb Amendment No. 95

-----.c;--\\

~---93*03020469 930223 PDR ADOCK 05000272 I

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ACTION 6 ACTION 7 ACTION 8 TABLE 3, 3-11 <cont:inw9 TABLE NOTATION With the number of OPERABLE chann~ls less than the Minimum Number of channels shown J.n Table 3.3-1:!., restore the inor:erable channel(s) co OPERABLE status within 7 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

With the number of OPERABLE channels one less than the Required Number of Channels shown in Table 3.3-11, operation may proceed until the next CHANNEL CALIBRATION (which shall be performed upon the next entry into MODE 5, COLO SHUTDOWN).

With the number of OPERABLE channels one less. than the Required or Minimum number of channels shown in Table 3.3-11, either restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or:

1.

Operation may proceed provided the Required Channels shown in Table 3.3-11 for the Reactor Coolant System Subcooling Margin Monitor and the Core Exit Thermocouples are OPERABLE.

With the number of OPERABLE channels for the Reactor Coolant System Subcooling Margin Monitor and the Core Exit Thermocouples shown in Table 3.3-11 less than the Required Number of Channels, follow the associated Action Statement, and

2.

Restore the system to OPERABLE status at the next scheduled CHANNEL CALIBRATION (which shall be performed upon the next entry into MODE 5, COLD SHUTDOWN).

SALEM e UNIT 2 3/4 3-Slc Amendment No. 95

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U1 U1 Kf'fACHMEN'f 2 TABLE,

3,3-+1 (CONTINUED)

ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT

13. PORV Block Valve Position Indicator

14. Pressurizer Safety Valve Position Indicator

15. Containment Pressure - Narrow Range

16. Containment Pressure - Wide Range

17. Containment Water Level -

Wide Range

18. Core Exit Thermocouple&

19. Reactor Veesel Level Instrumentation System (RVLIS)

REQUIRED NO. OF CHANNELS 2/valve**

2/valve**

2 2

2 4/core quadrant 2

MINIMUM NO. OF CHANNELS 1

1 1

2/core quadrant 1

ACTION 1, 2 1, 2 1, 2 7, 2 7, 2 1, 2 8

1, 2

(**) Total number of channels is considered to be two (2) with one (1) of the channels being any one (1) of the following alte~nate means of determining PORV, PORV Block, or Safety Vmlv~ positions Tailpipe Temperatures for the.valves, Pressurizer Relief Tank Temperature Pressurizer Relief Tank Level OPERABLE.

(***) Action 8 remains in effect until startup from the 10th refueling outage at which time, PSE&G will install the upgraded* RVLIS.

Upon expiration, Actions 1 and 2. will apply.

J.

e I

TMLE 3, 3*11 Ccpntim

TABLE NOTATIQN ACTION l Yith the number of OPERABLE accident monitoring channels less than the Required Number of Channels shown in Table 3.3-11, restore the inoperable channel(s) to OPERABLE status within 7 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 2 Yith the number of OPERABLE accident monitoring channels less than the MINIMUM Number* of Channels shown in Table 3.3-11, restore the inoperable channel(s) to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

~ --*71-ACTION 3 With the number of OPERABLE channels one less than the Required Number of Channels shown in Table 3.3-11, operation may proceed provided that the Boric Acid Tank associated with the remaining OPERABLE channel satisfies all requirements of Specification 3.1.2.8.a., otherwise comply with the requirements of 3.1.2.8

-:::::*:-::::::=:--..=:::""!"ac_~3:.?n ~-*--* --*- ___

__. ***--***---------~-- _. __ " ___ --------*--- _

ACTION 4

~ith the number of OPERABLE channels one less than the Required Number of Channels shown in Table 3.3.11, ~peration may proceed provided that an OPERABLE Steam Generator Yide Range Level channel is available as an alternate means of indication for the Steam Generator with no OPERATABLE Auxiliary Feedwater Flow Rate channel.

I I

,.~

ACTION 5 Yith the number of OPERABLE channels less than the Required Number of Channels show in Table 3.3-11.

operation may proceed provided that Steam Tables are available in the Control Room and the following Required Channels shown in Table 3.3-11 are OPERABLE to provide an alternate means of calculating Reactor Coolant System subcooling margin:

I.**

a.

Reactor Coolant Outlet Temperature - THOT (Yide Range)

b.

Reactor Coolant Pressure (Wide Range)

SALEM

UNIT 1

. 3/4 3-56 Amendment No. 117 I

I Y.*

.UCLEAR LICENSING WORK ST~ARD LICENSE CHANGE REQUESTS AND LICENSE AMENDMENTS NUCLEAR DEPARTMENT LICENSE CHANGE REQUEST APPROVAL FORM LCR Number C/cJ-/rJ-Uni t 54/@JM /Md g.

Initiating D~partment.~-L~/~O.~t?i~'ffr=-~f~/t1~~~r-------------------------~

Initiating Dept Sponsor Engineer __ /3'_;:-_. __

V:~,/i~~~tf//l.___;, ____________ ~-~---

Nuclear Licensing Sponsor Engineer __ t=

.~t/,~1~/A~OVt.._* ________________ ___:_

Tech Spec Numbers 33.3.) 4-ef;tiJ #3

(' J:,o/t, dlJ!fs)

Tech spec Title/subjectYast ArciA l '11011/rJ05 jJ~

DESCRIPTION OF CHANGE:

APPROVALS:

Nuclear Licensing Engineer-"~~=..;;..L.---------

Ini tiatinq Dept Sponsor~~~'.µ!=.===/+---------

Initiating Dept Manager -

Manager -

May 29, 1992 Page 10 of 13 Rev*~ o

~CLEAR LICENSING WORK ST~ARD LICENSE CHANGE REQUESTS AND LICENSE AMENDMENTS 1of2__

I.CR No._<<.....;;'%J..._-/_:J-__

Station/Unit 5 /! fJ-...

'Ihe p.irpose of the following checklist is to detenn.ine whether any special implementation considerations are asscx:::iated with the subject I.CR.

If the c.harqe requires :roore than 60 days following issuance to implement, or requires an outage, PSE&G must specifically request such implementation provisions frcm the NRC.

1.

Are any design :roodifications required for this change? (Y/N) fLl

/J'j:-=

If yes:

Has a DCP been campleted? (lllClude DCP #) ___

....:......!..1..._.__ __

Is an outage required to perfonn the :roodifications? (Y/N)

µ / /f

2.

Are any configuration changes such as changes to valve lineups, breaker positions or equipnent operating :roodes required ~ IJ1eet operability requirenelts as prop::ised by this change? (Y/N) __

/V __ _

If yes: List ch.an;es (Use Continuation Sheet if needed) * -----

/./ /-lft--

Is an outage required to perfonn the changes? (Y/N) __

. _/J ____ _

3. Will this c.harx;Je result in any new smveillance or inspection requirements? (Y/N) tJ If yes:

'(L/an outage required to perfonn the smveillance or inspection?

(Y/N)

4. List all procedures affected by the I.CR arrl identify the need for any new procedures (Use Continuation Sheet if needed).

1/1 Will it take greater than 60 days following issuance of the License AmeOOrnent to ilrplement the new or revised procedures? (Y/N) _ _._P ___ _

May 29, 1992 Page 11 of 13 Rev. o

~NUCLEAR LICENSING WORK ST~ARD LICENSE CHANGE REQUESTS AND LICENSE AMENDMENTS 2of~

I.CR No. C(J-/'J-Station/Unit D -I/,J-

SUMMARY

~

'lhe above change require more than 60 days to inplement followirg receipt of the amerx:tnent.

Licensing should request PQ '°days from the NRC.

D

'lhe above dlan3e require an outage to inplement.

pJ /fl-

'!his f o:cm should be completed and returned to the Nuclear Licensin:J contact for this I.CR within 21 days of receipt.

Licensin:J Contact ext.

~

Tech Spec Administrator

J' \\ V1-Technical Department (Sys. Eng) rJ I Ii\\.

Maintenance.Department

\\VI vi Procedure Upgrade Project Operations Department

"' l 11\\""

Technical Department (Procedures) tJ I ""°'

Rad Pro/Cllemistzy Department

- Required for all Salem License Cllange Requests.

May 29, 1992 Page 12 of 13 Rev. o

.NUCLEAR LICENSING WORK ST,.ARD LICENSE CHANGE REQUESTS AND LICENSE AMENDMENTS 3 of 3 I.CR No._q_a-_i_/_rJ.-_

Station/Unit ____ _

May 29, 1992 Page 13 of 13 Rev. o

ML18096B303

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SUMMARY

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