ML18086A878

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Proposed Revisions to Tech Spec 3.7.9 & 3.1.3.2.2 Re Snubber Testing & Rod Position Indication Sys
ML18086A878
Person / Time
Site: Salem  PSEG icon.png
Issue date: 08/10/1981
From:
Public Service Enterprise Group
To:
Shared Package
ML18086A875 List:
References
LCR-81-11, LCR-81-15, NUDOCS 8108180320
Download: ML18086A878 (25)
v • d • e


Text

PROPOSED CHANGE TECHNICAL SPECIFICATIONS SALEM UNITS 1 AND 2 DESCRIPTION OF CHANGE Ref: LCR 81-11 Technical Specification 3.7.9, Snubbers, should be revised to provide Limiting Conditions for Operation and Surveillance Requirements that agree with current NRC staff .positions and, at the same time, agree with each other for the two Salem Units. The existing Unit No.2 T.S. for snubbers, while being the more complete with regard to both hydraulic and mechanical snubber requirements has ambiguities in the wording of the visual inspection and functional testing sections that have been corrected in the proposed change. The proposed change also includes a listing of mechanical snubbers as required by the No. 2 Unit license conditions during the first four months of power operation.

  • REASON FOR CHANGE The proposed change satisfies NRC requirements for Salem No. 2 Unit and makes Units 1 and 2 agree with each other with respect to snubber LCO and Surveillance requirements.

SAFETY EVALUATION The proposed Technical Specifications modifications add new conditions for operation and more stringent testing requirements for the snubber systems of both units. Since none of the conditions of 10 CFR 50.59 are met, the change is not deemed to involve any unreviewed safety question.

PLANT SYSTEMS 3/4.7.9 SNUBBERS LIMITING CONDITION FOR.0PERATION 3.7.9 All snubbers listed in Tables 3.7-4a and 3.7-4b shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4. (MODES Sand 6 for snubbers located on systems required OPERABLE in those MODES). ACTION: With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.9c on the supported component or declare the supported system inoperable and follow appropriate ACTION statement for that system: SURVEILLANCE REQUIREMENTS 4.7.9 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5. a. Visual Insoection An inservice visual inspection of all snubbers listed in Tables 3.7-4a and 3.7-4b shall be performed in accordance with the following schedule for each separate Table: No. Inoperable Snubbers in a Table per Inspection Period 0 1 2 3, 4 5, 6, 7 8 or more Subsequent Inspection Period for each Table*# 18 months +/- 25% 12 months +/- 25% 6 months +/- 25% 124 days +/- 25% 62 days +/- 25% 31 days +/- 25% Within each Table, the snubbers may be categorized into two groups: Those accessible and those inaccessible during reactor operation.

Each group within a Table may be inspected independently in accordance with the above schedule.

  • The inspection interval shall not be lenghthened more than one step at a time. #The provisions of Specification 4.0.2 are not applicable.

SALEM -UNIT I 3/4 7-28 --*. . . -* ----..........

-* .. -** -.... -.........

--. *--* .. , I

.* .;I PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

b. Visual Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up. Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per cation 4.7.9d or 4.7.9e as applicable.

However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be declared inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.

All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.

c. Functional Tests At least once per 18 months during shutdown, a representative sample of 10% of the total of each type of snubber in use in the plant shall be functionally tested either in place or in a bench test. For each type of snubber that does not meet the functional test acceptance criteria of Specification 4.7.9d or 4.7.9e, an additional 10% of that type of snubber shall be functi anally tested. The representative sample selected for functional-testing shall include the various configurations, operating environments and the range of size and capacity of snubbers.

At least 25% of the snubbers in the representative sample shall include snubbers from the following three categories:

1. The first snubber away from each reactor vessel nozzle 2. Snubbers within five feet of heavy equipment (valve, pump, turbine, motor, etc.) 3. Snubbers within ten feet of the discharge from a safety relief valve Snubbers identified in Tables 3.7-4a and 3.7-4b as "Especially Difficult to Remove 11 or in "High Radiation Zones During Shutdown" shall also be included in the representative sample.* Tables 3.7-4a *Permanent or other exemptions from functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date. SALEM -UNIT I 3/4 7-2, I I.

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) and 3.7-4b may be used jointly or separately as the basis for the sampling plan. In addition to the regular snubbers which failed the previous functional test shall be retestedduring the next test period. If a .spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested.

Test results of these snubbers may not be included for the re-sampling.

If any snubber selected for functional testing either fails to lockup or fails to move, frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all snubbers of the same design subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.

  • For the snubber(s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber(s).

The purpose of this engineering evaluation shall be ta determine if the components supported by the snubber(s) were adversely affected by the inoperability of the snubber(s) in order to ensure that the supported component remains capable of meeting the designed service. d. Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that: 1. Activation (restraining action) is achieved within-the specified range of velocity or acceleration in both tension and compression.

2. Snubber bleed, or release rate, where is within the specified range in compression or tension. For snubbers specifically required to not displace under continuous load, the ability of the snubber**to withstand load without ment shall be verified.
e. Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that: 1. The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force. *The drag force shall not have increased more than 50% since the last functional test. 2. Activation (restraining action) is achieved within the specifiea range of velocity or acceleration in both tension and compression.

SALEM -UNIT I 3/4 7-3<> I

Pt.ANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

3. Snubber release rate, where required, is within the specified range in compression or tension. For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.
f. Snubber Service Life Monitoring A record of the service life of each snubber, the date at which the designated service life commences and the installation and ance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.1.

Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for each snubber listed in Tables 3.7-4a and 3.7-4b shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review. If the indicated service life will be exceeded prior to the next scheduled snubber service life review, the snubber service life shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review. This reevaluation, replacement or reconditioning shall be indicated in the records. SALEM -UNIT t 3/4 7-11 TABLE_]_.

7-4A I II . VI )> SAFETY RELATED HYDRAULIC SNUBBERS*

r-l'T1 3: I c= :z SNUBBER SYSTEM SNUBBER INSTALLED ACCESS IBLE OR HIGll RADIATION ESPECIALLY DIFFICULT

....... -f NO. ON, LOCATION AND ELEVATION INACCESSIBLE ZONE** TO REMOVE ..... ---\A or I) (Yes or No) (Yes or No) 1 No. 11 Steam Generator, Reactor Yes Yes Containment, Elev. 128' 6" 2 . No. 11 Steam Generator.

Reactor I Yes Yes Containment, Elev. 128' 6 11 3 No. 11 Steam Generator, Reactor I Yes Yes Containment, Elev. 128' 6 11 -4 No. 11 Steam Generator, Reactor I Yes Yes w Containment, Elev. 128' 6 11 ........ " 5 No. 12 Steam Generator, Reactor I Yes Yes -:. -Containment, Elev. 128' 6 11 , J"' 6 No. 12 Steam Generator, Reactor I Yes Yes Containment, Elev. 128' 6 11 7 No. 12 Steam Generator, Reactor I Yes Yes Containment, Elev. 128' 6 11 8 No. 12 Steam Generator, Reactor I Yes Yes Containment, Elev. 128' 6 11 -

3.7-1\\(Continued)

I Vl )> SAFETY RELATED HYDRAULIC SNUBBERS*

r-fT1 3: I c:: :z SNUBBER SYSTEM SNUBBER INSTALLED ACCESS IBLE OR HIGH RADIATION ESPECIALLY DIFFICULT

...... --4 NO. ON, LOCATION AND ELEVATION INACCESSIBLE ZONE** TO REMOVE _. (A or I) (Yes or No) (Yes or No) 9 No. 13 Steam Generator, Reactor I Yes Yes e Containment, Elev. 128' 6" 10 No. 13 Steam Generator, Reactor I Yes Yes Containment, Elev. 128' 6" 11 No. 13 Steam Generator, Reactor I Yes Yes Containment, Elev. 128' 6" \ H. 12 No. 13 Steam Generator, Reactor I Yes Yes w Containment, Elev. 128' 6" -.i:. *; ...... I 13 No. 14 Steam Generator, Reactor I Yes Yes w Containment, Elev. 128' 6" .,. 14 No. 14 Steam Generator, Reactor Yes Yes Containment, Elev. 128' 6" 15 No. 14 Steam Generator, Reactor I Yes Yes Containment, Elev. 128' 6" 16 No. 14 Steam Generator, Reactor I Yes Yes Containment, Elev. 128' 6 11 -

, ' ' *1 I ,\ " ' J -l ; I l 1 VI )> r ...., 3: I c z ....... .....

  • I!\!3.LI_]_. (Continued)

SAFETY RfLATED llYORJ\ULIC SNUBBERS*

SNUBBER NO. SYSTEM SNUBBER INSTALLED

_9CJ\ T _I ON

__

ACCESS IBLf OR JNACCESS IBLE ** * --ucar*-rr--HIGH RADIATION ZONE** --{Yes-orNo/ ESPECIALLY DIFFICULT TO REMOVE or NOT--11. 23. al-. No. 11 Main Steam Isolation Valve Penetration Area, Elev. 115' 5" No. 11 Main Steam Isolation Valve Penetration Area, Elev. 115' 5" No. 12 Main Steam Isolation Valve Penetration Area, Elev. 115' 5 11 No. 12 Main Steam Isolation Valve Penetration Area, Elev. 115' 5" No. 13 Main Steam Isolation Valve Penetration Area, Elev. 115' 5 11 No. 13 Main Steam Isolation Valve Penetration Area, Elev. 115' 5" No. 14 Main Steam Isolation Valve Penetration Area, Elev. 115' 5" No. 14 Main Steam Isolation Valve Penetration Area, Elev. 115' 5" A A A A A A A A No No Y*s No Y*s No No Ves No '/es No Yet; No 'fes

  • Snubbers may be added to safety related systems without prior License Amendment to Table 3.7-4 provided that a revision to Table 3.7-4 is included with the next License Amendment request. **Modifications to this table due to changes in high radiation areas shall be submitted to the NRC as part of the next License Amendment request. \ I 11. .1 J.

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YES/NO YE' S. '{e:s "I g-s 'le s 'f *> "1 'I £"S YES -Yc-s Ye-s y £S '(E. s yES YES yt;5 '/f S YC.-S ESPECIALLY DIFFICULT TO ROOVE? YES/NO NO tvo ,VO " N"o NO N'c> l'J o r..r a l \ NO fJO N r>

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A I I I .I .I I .:L I .L I :r -:r: I 'T I I I .:r I I .:r r HIGH RADIATION ZONE** ,.. DURING SHUTDOWNf YES/NO ie:c; '/ES "1t:=S t r=s "(e-s '/ E""S "f£'> Yes }'E:S YE:S YE> "/ES '/*5 ;'E.s YES YE<; YES Y*5 Y*) ESPECIALLY DIFFICULT TO ROOVE? YES/NO NO "16 NO NO Nf> N?J NO NO ' NO NO "'°

....,o Ntl ND '{£S YcS cf\ )> r rn c l. -. i -' I ) I .1 I I l -1 ' w N 0-' .\ 1 .. ; ' SNUBBER NO. 41 C/2. c/3 -'I</ </) '/7 t/.k' C;.C> )I sl. rJ . >f )5' 57 )J' t;o TABLE 3 .7-48 SAFETY REL.A TED I CAL SNUBBERS

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YES/NO 'lt5> 'IES '/t.5 '{tS "f e::s °YES NG rJ 0 ""Q "'f CS "'IE3 '(E5 --/ES YES YcS N'O l't 11 l'JO ESPECIALLY DIFFICUL TO ROOVE? YES/NO '/ES 'IE t; '(E'S N tJ'() f'J 0 rJCl .,r 0 * "1"0 NO tJo NO tJ 0 rJO NO I ! i ! i i I I . i ' I l 1 1 ' ] I ' i *l . l 1 1 l *.1 j ! I -: . i 1 ;i ; I j ., i c: ?. -TABLE 3.7-4a SAFETY REU\TED MECHANICAL SNUBBERS

  • SNUBBER NO. SNUBBER INSTALLATION INFORMATION SYSTEM LOCATION ELEVATION HIGH RADIATION ACCESSIBLE OR ZONE** ESPECIALLY DIFFICULT DURING SHUTDOWN?

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  • Snubbers may be added to safety related systems without prior License Amendment to Table 3.7-4* provided that a revision to Table 3.7-4b is included with the next License Amendment request. **Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that a revision to Table is included with the next License Amendment request. ' }.J ti PLANT SYSTEMS 3/4.7.9 SNUBBERS LIMITING CONDITION FOR.0PERATION 3.7.9 All snubbers listed in Tables 3.7-4a and 3.7-4b shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3 and 4. (MODES 5 and 6 for snubbers locate*d on systems required OPERABLE in those MODES). ACTION: With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.9c on the supported component or declare the supported system inoperable and follow appropriate ACTION statement for that system. SURVEILLANCE REQUIREMENTS 4.7.9 Each snubber shall be demonstrated OPERABLE by performance of the following augmented inservice inspection program and the requirements of Specification 4.0.5. a. Visual Inspection The first inservice visual inspection of snubbers shall be performed after four months but within 10 months of POWER OPERATION and shall include all snubbers listed in Tables 3.7-4a and 3.7-4b. If less than two (2) snubbers 1 in the same Table are found inoperable during the first insei-vice.visual inspection, the second inse:r:vice visual inspection for snubbers in that Table shall be performed 12 months +/- 25% from the date of the first inspection.

Otherwise, subsequent visual inspections shall be performed for each separate Table in accordance with the following schedule:

No. Inoperable Snubbers in a Table per Inspection Period 0 1 2 3 I 4 5, 6, 7 8 or more Subsequent Inspection Period for each Table*# 18 months +/- 25% 12 months +/- 25% 6 months +/- 25% 124 days +/- 25% 62 days

  • 25% 31 days +/- 25% within each Table,. the snubbers may be categorized into two groups: Those accessible and those inaccessible during reactor operation.

Each group within a Table may be inspected independently in accordance with the above schedule.

  • The inspection interval shall not be lenghthened more than one step at a time. #The provisions of Specification 4.0.2 are not applicable.

SALEM -UNIT t 3/4 7-23 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) and 3. 7-4b may be used jointly or separately as the basis for the sampling plan. In addition to the regular sample, snubbers which failed the previous (I functional test shall be retestedduring the next test period. If a .spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested.

Test results of these snubbers may not be included for the re-sampling.

If any snubber selected for functional testing either fiils to lockup or fails to move, i.e., frozen in place, the cause will be evaluated and if caused by manufacturer or design deficiency all snubbers of the same design subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated above for snubbers not meeting the functional test acceptance criteria.

For the snubber(s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber(s).

The purpose of this engineering evaluation shall be to determine if the components supported by the snubber(s) were adversely affected by the inoperability of the snubber(s) in order to ensure that the supported component remains capable of meeting the designed service. d. Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that: 1. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.

2. Snubber bleed, or release rate, where required, is within the specified range in compression or tension. For snubbers specifically required to not displace' under continuous load, the ability of the snubber to withstand load without ment shall be verified.
e. Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify that: 1. The force that initiates free movement of the snucber rod in either tension or compression is less than the specified maximum drag force. The drag force shall not have increased more than 50% since the last functional test. 2. Activation (restraining action) is achieved within the specifiea range of velocity or acceleration in both tension and compression.

SALEM -UNIT 2 3/4 7-25 Vl )> r tn 3: c :z t-i -I N w .........

""' "'""' I N lO TABLE 3.7-4a (Continued)

SAFETY RELATED HYDRAULIC SNUBBERS*

SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR HIGH RADIATION ESPECIALLY DIFFICULT NO. ON 1 LOCATION AND ELEVATION INACCESSIBLE DURING SllUTDOWN**

TO REMOVE (A or I) (Yes or No) (Yes or No) 17 . No. 21 Main Steam Isolation Valve A No Yes Penetration Area, Elev. 115 1 511 18. No. 21 Main Steam Isolation Valve A No Yes Penetration

Area, 115 1 5 11 19. No. 22 Main Steam Isolation Valve A No Yes Penetration Area, Elev. 115 1 5 11 No. 22 Main Steam Isolation Valve A No Yes Penetration Area, Elev. 115 1 5 11 21 . No. 23 Main Steam Isolation Valve A No Yes Penetration Area, Elev. 115 1 5 11 l2. No. 23 Main Steam Isolation Valve A No Yes Penetration Area, Elev. 115 1 5 11 Z3. No. 24 Main Steam Isolation Valve A No Yes Penetration Area, Elev. 115' 511 za/. No. 24 Main Steam Isolation A No Yes Penetration Area, Elev. 115 1 5 11
  • Snubbers may be added to safety related systems without prior License Amendment to Table 3.7-4Q.provided that a revision to Table included with the next License Amendment request. ** Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that a revision to Table included with the next License Amendment request. -I (-"' ta* , . ..,o* ..> Jr" TABLE 3 .7-4a SAFElY RELATED I CAL SNUBBERS
  • SNUBBER NO, SNUBBER INSTALLATION INFORMATION SYSTEM LOCATION ELEVATION 11-.\.

I (4\'-3 ......_:.--t--E. Q.\J.A P. ,, I ti PRi;::i.s'R.*

c.. 14 -:l. 'S. E. Q, UA.p, 4 \N. PRli!5S' \ >. 0 *.,.., )..1, e. Cil VA, D, '-\-0 'O 5 PR*.ss'R*

l'-l*W* Q\UAD,

  • G;, I N. PR *SS' g ' l41 '-0 11 \'1. E: *.

ACCESS IBLE OR INACCESSIBLE?

A I I r HIGH RADIATION ZONE** ,.. DURING SHUTDOWNf YES/NO

  • ESPECIALLY DIFFICULT TO REM:>VE? YES/NO .LL PRESS' g. \A '!l' .. Q" S. W. Ol..UAt::>, -

\t 1 f'\\. PR Ess*g. 1 , IN S'.e. G.VAD. l S' '-B A __:..J .t\\VA.2P8*41__

_____

_, \ YRE°SS'F:*

\L't_'-B" .----....--1._,.

___ s_._._WL.lr__;;GJ..V-'-1'

__ r.>_ .. _. ____ , __ ::>'D __ -l+ __

15 1 1 s'-o _ S. {t:, G vAD '"T ft, l't\ Pt2£$c;t '2..* 4 O"

  • 17 PR.e.>s'1Z-*

14SLo

_________

µ 18 \No 15"'-B

J * . 1 14\'-o I 1 1 -'

--; ;------rt:J

......_ ____ _.. __ _i_ __ i--_ _,!_ __ _ . 5.W.

l6t l:. lES NC)

L SNUBBER NO, _21 _2?.. 23 _24 25' _2G 1 z7* 28 29 -:,o 31 31 -33 *34 2>(, 37 ,.--* 38 ,.----a9 "*-. **-* 40 ' TABLE 3 .7-48 SAFETY RELATED MEO-lAN I CAL SNUBBERS

  • SNUBBER INSTALLATION INFORMATION SYSTEM LOCATION ELEVATION Re>GT LOC.

C'OCUijf -II 11 II ..

856' --Lac. '"".

1 r3EC.T. B9*3

,, .. 92* .. ' LOC, BtiT. f>e-4

,, It It eve LO:,@ S\Of."t1 RCP Pl. !FM d WALL Ice

"'*e.

10\ . _Ef: U: 1.1-RC'P Loe, NT. Wffr su:.E of cc. rt 24 R<:'P PlfFM i WALL

"'S. *** , \1-l \.l to\ v Lu 5 0.

es'.'} l-oc

  • AAl.llJLUS I . . ao*-!:

---* Loe. SET.

F"R, e*FR.

.. Loe. e1i1r. s.w. S1De: 88 '-1 PE U""l4 RS?

Loe. Bli'i, il 2{ ST. 4 e,iJ FRAME l CAA HE WALL Loe.

COf\t.IElt-93' e:, -0 I-

-Loe. 8Et. So, S1p.e oi:-<c:' Pl\Uf,

-<o !'IoQ.'f"I-\

o¢ ' G> Pteu. 1 # l?'/i wr;sr OF JJ' AReA l08-1 . -14*-1 11 t--lof\n\OP\l.b -r" d\'!*!1 . * -Lo

  • IU ---' I *Ir 9'f WG.Si oF Vz' -ACCESS IBLE OR I IBLE? A I I I ' ' 1 r I A A I HIGH RADIATION ZONE** ..... DURING SHUTDOWN( YES/NO

'/E:S NO NO tJO NO '(CS '/ES t-J 0 "10 '/E'S °'(ES iE:S 1E'S NO tJ Q NO ESPECIALLY DIFFICULT TO ROOVE? YES/NO Na ' '

  • 1* No If'. l> r m c t 1J SNUBBER NO. 41 42 l/3 -ti'-/ </{ <I' -l/7 <1r 49 S1l)/ )Z 53 r-</ S-5' S :>7 S-6" S-'"t ,0 .....____

TABLE 3.7-4a SAFEIY RELA IBJ I CAL SNUBBERS

  • SNUBBER INSTALIJ\TION INFORMATION SYSTEM LOCATION ELEVATION Ii L to6. @ s. \it. co AAf1L -oF # sr. <i Et-1. Flt.* ...

i *-co** r-loR'lt\ \<O, "l. S p G/J 8B'-3 Sf'RA'( (p'-7.11 WliST oi: G G __:__ ST, (.i""4. '2 3 J-to, o F 'Z.

FDWTR. !

Ol=t>-e. -... -* I ,, It \)Q 10" No, o F' '"* i' I 'Z.'-o EAST OF oe 130 1-<;, ! "

l3o'-'=f' l

  • Loe:, IJ Utt.. N, $>E,..J \'2.8 1-10" E.A5T WA'-L ** l 'l8 1-ld' _I l.OC: I OVTS' C>t:!. .. (=," eAST W>tLL. 'I --._

oi: 16.i

'-C::' W£ST a F .()e.. ' ,, 14 fl_

' _, /' ._ tt " I I "

/fl II " l?a \' .. t tt ". I '

--L0<:. K\, a* fJ,J'erJ.

,, II

,.r ,, i; 1 1-z *' 1 I 11 -1;1 1-z l'.P-4" Na. oF I 1=1>Wnt S.PEN. 102!. V' -MA>\.l '27 ! 7" NOf OF l Gi. "l. S.PEN. n2'-o" ST* 1>fll'l* e *-F. ACCESS IBLE OR I IBLE? A I I r A 4

  • r A HIGH RADIATION ZONE** ,.., DURING SHUTOOWNf YES/NO "IES NO 0 \ , , NO -----------ESPECIALLY DIFFICULT TO ROOVE? YES/NO N'O j ' -l -1 , NO -------I I I f SNUBBER NO, t;, I c.z. Cr.I ,, ,, -t;7 ,9 /o ....,, ?1-'7 3 14 7, 77 "l "' 71 30 TABLE 3.7-4a SAFElY RELATEIJ I CAL SNUBBERS
  • SNUBBER INSTALI.ATION INFORMATION SYSTEM LOCATION ELEVATION 11'WfAm No. oF l'b:'L \\ 'l. t. o i DfU( __ , AREA o:>'-'i.'>*

4' WEST oF DC MAi1r 0F'1"li).Z

' Jf, PP.ij OF DC. . lD3-'3 11 1 AVr<* 111.lif >:10 1 ot= 14-94'-1 !ti'I

_BLC4 RR II It °>4 ' .. 1 1 1Z' i ,

o F' 14'. ! 4

  • g.>S1 OF LL 1 i!. ')" of= 14-21..1 o" Ell.Si o F Lt. 94'-1 I So. 11,co AReA 1L o 11 EAST ot= "\-\ I 87 \ II .. I 1 !1 11.b OF \l. \-\ ---*-I\ II -I 85-0 --

OF Ho, i. 1 (," -*-oF H\-\ J , f t\ "

0 IAVK, No,

.. 1 BLDq. ';l!. loEAST of: 5 5 I II II BG:>'-\" I , lV or l"h a 78'-0 I }'1 WflS'T OF \J. \-\ I 4' .. 0 So, Or \<;l,-z. . . lt'-0 WEST OF ---illlb' o\iffi oTfs;/ -* 92!0" <6'-?JEASf \...L ,_ -tr 11 t . --1 \1c.. ..

of' 1s.1 . . 1-I -

[;AST OF

-'I I-! , -.. .. ACCESSIBLE OR INACCESSIBLE?

A I I A p ' I A HIGH RADIATION ZONE** r DURING SHUTDOWNf YES/NO NC " v* ESPECIALLY DIFFICULT TO REMOVE? YES/NO NO I* ,, No .1

....) I w 0 ,S2_ SNUBBER NO. 8\ AZ B3 84 85 -8b 87 8'? 8 9D '11 TABLE 3.7-4A SAFETY REL.A TED I CAL SNUBBERS

  • SNUBBER INSTALl.ATION INFORMATION SYSTEM LOCATION ELEVATION ACCESS IBLE OR I IBLE? HIGH RADIATION ZONE** ,., DURING SHUTDOWNf ESPECIALLY DIFFICULT TO ROOVE? A I I YES/NO YES/NO I 1 oF \5,1 -

A NO '.!1 ..

o£lj..

n 'Rb* s 9. oF \s .. 1 1 8 1-7!"ttJ' EAST OF LL ,. !

eAST OF LL ---c.vc B ..

  • s,, OF 1s.1 I \ 0 \ !..1 \ ... 5" wrsr oF 1 cc So. OF It;;, 1 ! %'-o

OF GG I cc " ,, I Ir 9ro'-o" H df \1 ) --... / ,/ / '[) etE;ED -f2.*f'(ACJ::.-r:>

"""' I TH fZt (rl {) / / /. \ '5"1"12-"rr.s

/ / / _) / I/ I/ SPet-IT' Av)(, 9 I ,, A

'2-3 PJ'c) C004..INI.

St..DIP-.

  • Snubbers may be added to safety related systems without prior License Amendment lo Table 3.7-41t providetJ lhat a revision lo Table 3.7-4a. is included with the next License Amendment request.

to this colunin due to changes in high radiation areas may be made without prior License Amendment provided that a revision to Table 3.7-4., is included with the next License Amendment reque!it.

  • PROPOSED CHANGE TECHNICAL SPECIFICATIONS SALEM UNIT NO. 2 DESCRIPTION OF CHANGE .LCR 81-15 Technical Specification 3.1.3.2.2., Position Indication System -Shutdown, should be revised to read: "In_addition to the Demand Position Indication System, which shall be OPERABLE, one rod ition indicator shall be capable of determining outward movement during withdrawal for each shutdown or control rod and be capable of indicating approximate position for each shutdown or rod not fully inserted in the core". The ACTION should read, "With less than the above required capability, rod withdrawal may continue to 100 steps (by Demand Position Indication).

If the above required rod position indicator capability still cannot be satisfied, stop all rod withdrawal and either: a. restore the required position indicator(s) capability within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or b. open the reactor trip system breakers".

REASON FOR CHANGE The proposed changes provide operating latitude for the al of shutdown/control rods in Modes 3, 4, and 5 urider conditicns of temperature and magnetic flux instability thc.t cause wide iations in rod position indication.

When these external ing effects stabilize to values for which the RPI's are ed, the indication meets the present requirements of the cation; but, the present specification requires immediate opening of the reactor trip breakers, allowing neither time for tion nor allowing for cold plant conditions effects. SAFETY EVALUATION As stated in the BASES for Reactivity Control Systems, the ifications of section 3/4.1.3., Movable Control Assemblies, ensure that: 1. acceptable power distribution limits are maintained

2. the minimum SHUTDOWN MARGIN is maintained
3. potential effects of a rod ejection accident are limited This specification is applicable in Modes 3, 4, and 5; tnere are no Unreviewed Safety Questions involved in this change since: 1. there are no power distribution considerations for Modes 3, 4, and 5 , 2. rods that are not fully inserted provide more SHUTDOWN MARGIN than when they are fully inserted . , 3. the effects of a rod ejection accident are less severe for a partially withdrawn rod than for one that is ejected from a fully inserted position.
  • REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEM-SHUTDOWN LIMITING CONDITION FOR OPERATION
3. 1.3.2.2 One rod position indicator (excluding demand position indication) shall be OPERABLE and capable of determining the control rod position within +/- 12 steps for each shutdown or control rod not fully inserted.

APPLICABILITY:

MODES 3*#, 4*# and 5*#. ACTION: With less than the above required position indicator(s)

OPERABLE, immediately open the reactor trip system breakers.

SURVEILLANCE REQUIREMENTS

4. 1.3.2.2 Each of the above required rod position indicator(s) shall be determined to be OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 18 months. *With the reactor trip system breakers in the closed position.
  1. See Special Test Exception
3. 10.5. SALEM -UNIT 2 3/4 1-17
  • REACTIVIJY CONTROL SYSTEMS POS III ON I NOi CATI ON SYSTEM -SHUTDOWN LIMITING CONPITIQN "FOR OPERATION.

3.1.3.2.2 In addition to the Demand Position Indication System, which shall be OPERABLE, one rod position indicator shall be capable of detennining outward noverrent during withdrawal for each shutdown or control rod and be capable of indicating approximate position for each shutdown or control rod not fully inserted in the core. APP LI CABI LIJY ACTION : fvDDES 3*#, 4*#, and 5*#. With less than the above required capability, rod withdrawal may continue to 100 steps (by Demand Position Indication).

If the above required rod position indicator capability still cannot be satisfied, stop all rod withdrawal and either: a. restore the required position indicator(s) capability within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or b. open the reactor trip system breakers.

SURVEILLANCE REQUIREMENTS

4. 1.3.2.2 Each of the above required rod position indicator(s) shall be determined to be OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 18 months. *With the reactor trip system breakers in the closed position.
  1. See Special Test Exception
3. 10.5. SALEM -UNIT 2 3/4 1-17
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