ML20198L678

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Transmits Summary of Joint Nrc/Tss Task Force Owners Group Meetings on 971001-02 in Rockville,Md
ML20198L678
Person / Time
Issue date: 10/21/1997
From: Beckner W
NRC (Affiliation Not Assigned)
To: Jennifer Davis
NUCLEAR ENERGY INSTITUTE (FORMERLY NUCLEAR MGMT &
References
NUDOCS 9710270117
Download: ML20198L678 (16)
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Text

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OctobGr 21, 1997 Mr. James Davis-Nuclear Energy Institute 1776 Eye Street, N. W.

Suite 300

.Washington, DC i20006 2496'

Dear Mr. Davis:

The purpose of this letter is to transmit a summary of the joint NRC/ Technical Specifications Task Force (TSTF) Omer's Group meeting, which took-place at the Nuclear Regulatory Commission in Rockville, Maryland, on October 1 and 2. 1997.

Sincerely, 70'riginal Signidly William D. Beckner. Chief Technical Specifications Branch Office of Nuclear Reactor Regulation

Enclosure:

As stated cc: See attached DISTRIBUTION:

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Washington, DC 20006 2496 4

Dent Mr. Davis:

The purpose of this letter is to transmit a summary _of the joint NRC/ Technical Specifications Task Force (TSTF) Owner's Group meeting, which took place at the Nuclear Regulatory Commission in Rockville, Maryland, on October 1 and 2,1997.

Sincerely, Q&& D. &W William D. Beckner, Chlaf Technical Specifications Branch Office of Nuclear Reactor Regulation

Enclosure:

As stated cc: See attached l

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TECHNICAL. SPECIFICATIONS TASK FORCE MEETING

SUMMARY

October 1 and 2, 1997 Meetings betwee the NEI Technical Specifications Task Force (TSTF), and NRC

-s at ff were held on October 1 and 2,1997. The attendees list is Attachment 1.

Comments on Meeting Summary of August 28.-1997 Meeting Ms. Johnson asked _for coments on the meeting stamary transmitted to James Davis, Nuclear Energy Institute, by letter dated September 4,1997. -There were no coments on the meeting minutes, Status of Pending Traveler TSTF-135. RPS and ESFAS Instrtmentation Specifications -!

Carl Schulten provided a hand-out containing_ 30 questions and responses

-(Attachment 2), Discussion of questions 1, 2, 4, 5, 6, 7, 8.-9, and 24 ensued.

The_ Owner's Group requested a 10 minute break to discuss the hand out, after which they agreed to look at the entire list of questions and address later in the meeting After the lunch break, representatives from Instrumentation and

. -Control Branch, Carl Schulten and Dan Williamson, WOG, had a break-out ineeting.

It was' decided that the TSTF would submit a revision to TSTF-135.

Status of Pending Travelers Those travelers that were approved by NRC during the 10/1-2/97 joint NRC/TSTF l Owner's Group meeting were:

TSTF-69, -71, R.1, -72

  • -73, 76, -81, and -124 Those travelers that were recommended for approval by the NRC reviewer during the 710/1-2/97 joint NRC/TSTF Owner's Group meeting were:

. TSTF-23. R.2, -79, R.1, -80, R.1, -82, R.1, -85,:R.1, -93, R.3, -128 R.1,

-130, R.1, -133, R.1, -162. -169, -170. -172. -177, -178. -179 -180.

-181, -182, -184. -185, -186, -187. -188. -189. -192, and -195 1

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Those travelers that were modified by NRC during the 10/1 2/9/ joint NRC/TSTF avner's Group meeting were:

  • TSTF 19, R.I. The TSTF agreed to submit a revision containing NRC's proposed changes, t
  • TSTF 65 should be modified to include use of brackets in the Bases as well as the specs. On 10/2/97, the TSTF submitted TSTF 65 Rev.1 (see Attachment 3) and the reviewer recommended approval.
  • TSTF 87. Rev.1, should be modified to provide a supplement to the bases statement describing why change is necessary. TSTF 87. Rev. 2, was submitted on 10/2/97 and the reviewer recommended approval.
  • TSTf 93, Rev. 2. should be modified to also include Insert 1 in the Bases arid remove statelnent regarding frequencies. TSTF wil's submit a revision package (see Attachment 3).
  • TSTf 103 was modified by NRC in April. The staff wants one 3.0.4. The TSTF will review and may resubmit in the future.
  • TSTf-110. Rev.1, is unacceptable as submitted. A revision should be submitted containing a statement / justification that this change will have no adverse impact on safety. TSTF submitted a revision on 10/2/97 (see Attachment 3) and the reviewer recommended approval.
  • 'ISTF 127, as submitted. is not acceptable. The NRC suggested the justification is not adequate: is based on rod movement SR frequency, not equipment reliability. On 10/1/97, the TSTF submitted TSTf 127. Rev. 1 (see Attachment 3) and the reviewer recommended approval.
  • TSTF-128 contained a justification that is technically incorrect and should be modified. TSTF will submit a revision to include the proposed modification (see Attachment 3).

Those travelers that were rejected by NRC during the 10/1-2/97 joint NRC/TSTF avner's Group meeting were:

The TSTF wishes to appeal the rejection and will contact the reviewer for a future meeting.

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  • TSTF 119 was reconnended to be rejected by the Plant Systems Branch.

William Beckner agreed with the recommendation and rejected the proposed changes.

  • TSTT 163 was rejected by NRC in a 9/22/97 letter to NEl. The TSTF wishes to appeal the rejection and will contact the reviewer for a future ,

meeting.

  • TSTF 196 was rejected by NRC. The TSTF wishes to appeal the rejection ,

and will contact the reviewer for a future meeting.

Those travelers that were withdrawn by the TSTF during the 10/12/97 joint NRC/TSTF Owner's Group meeting were:

  • TSTFs 64 88, 145, and 183 were withdrawn by the TSTF.

Those travelers that remain pending after the 10/1 2/97 joint NRC/TSTF Owner's Group meeting are:

  • TSTF 27, Rev. 2, is pending Reactor Systems Branch review.
  • TSTF 51 is CBLA related and a lower priority than STS Conversions
  • TSTF 58 is awaiting the Risk Informed Technical Specification pilot approvals.
  • TSTF-59 1s awaiting the Risk-Informed Technical Specification pilot approvals.
  • TSTF 68 Re.'.1 is CBLA related and a lower priority than STS Conversions
  • TSTF-91, Rev.1, is being referred to the Electrical Engineering Branch for review. ,
  • TSTF-92, Rev.1, is pending Reactor Systems Branch review.
  • TSTF-111, Rev.1, is pending the outcome of a TSB/HICB meeting.
  • TSTF-113. Rev.1, is pending receipt of Revision 4 from the TSTF.
  • TSTF-116. Rev.1. is pending Reactor Systems Branch review.

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. TSTfs 135. 154 R 1, 168. 171, 190, and 191 are pending further review,

. 1STf 197 is pending Reactor Systems Branch review: the TSTF will also submit a revision package to retain the change in Actions.

  • By letter dated 4/9/97, via TSB Oll, NRC proposed changes to the Administrative Controls Section of the STS to accommodate chance to 10 CFR 20 and 10 CFR 50,36a, the staffing requirements in 10 CrR 50 and 55, and to include a new staff position regarding controls for the working hours of personnel who perfore safety related functions. The TSTF reported in the 10/12/97 meeting that they have converted TSB 011 into a TSTF traveler and are ready to submit it to NRC, Other Meetino Topics Sixty six pending travelers were discussed during this two day meeting. Out of these sixty six, twenty eight rertin pending. Of the remaining pending travelers, the TSTF identified fourteen that they would like NRC to assign priority review. Those TSTF are, not necessarily in this order. 2, R,2 27.

R,2, 36. 37. -Ill, R,1, 135, 198. -199. -200, 201. 202. -203. 204, and -

205*.

The next meeting of the NRC/TSTF Osmer's Group will be November 5 and 6,1997 in room 0 3 B4,

  • This traveler will be submitted in the near future.

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Attachment 1 ATTENDEES LIST NRC/TSTf OWNER'S GROUP MEETING October 1 and 2.1997 NAME ORGANIZATION ADDRESS PHONE # J. KAll 10 James Davis Nuclear Energy 1776 Eye Street. NW 202 739 8105 jwdDnei.org Institute Washington. DC 20006 (NEI)

Bryan ford BWROG Entergy Services. Inc. 601 368 5792 bford@

1340 Echelon Parkway. entergy.com H ECH 660 Jackson MS 39213 8298 Clinton Szabo BWOG/E01/ANO 1448 S. R. 333 501 858 4622 cszabo@

Russellville, AR 72801- entergy.com 0967 John Volkoff CEOG/BGE 1650 Calvert Cliffs 418 495 3649 John.Volkoff@

Parkway BGE.com Lusby. HD 20657 4702 Dan William 30n WOG 271 Glenlyon Dr. 904 272 5300 dwdan@

Orange Park. FL 32073 msn.com Donald Hoffman EXCEL /TSTF 11921 Rockville Pike 301 984 4400 donaldh@

Suite 100 excelsvcs.

Rockville. HD 20852 com Glen Ohlemucher Detroit Edison 6400 N. Dixie Hsy 313 586 4275 oblemucher@

Newport. HI 48166 detroitedison

.Com Charles Boyce DEC0/ fermi 2 8 Daylily Drive 609 866 5624 karmaone@

Ht. Laurel. NJ 08054 msn.com William Beckner NRR/TS8/ADPR NRC 301 415 1161 wdb@nrc. gov Mark Reinhart NRR/TS53/ADPR NRC 301 415 1161 fmr9nrc. gov Angelo Marinos NRR/HICB/DRCH NRC 301-415 2911 ecm@nrc. gov Page 1

Attachment 1 ATTENDEES LIST NRC/TSTF OWNER'S GROUP MEETING October 1 and 2. 1997 NAME ORGANIZATION ADDRESS PHONE # E Mall ID Berry Marcus NRR/HICB/DRCH NRC 301-415 2823 bsm@nrc. gov Steve West NRR/SPLB/DSSA NRC 301 415 1220 ksw@nrc. gov Chu Yu Liang NRR/SRXB/DSSA NRC 301 415 2878 cyl@nrc. gov Jim Wigginton NRR/PERB/DRPM NRC 301 415-1059 jew 2@nrc. gov Steve Klementowicz NRR/PERB/DRPM NRC 301 415 1084 sxk@nrc. gov Kamal Manoly NRR/EMEB/DE NRC 301 415 2765 kam@nrc. gov Y. C. Li NRR/EMEB/DE NRC 301 415 2772 ycl@nrc. gov Sinon Sheng NRR/EHCB/DE NRC 301-415 2708 sheng@nrc. gov Debbie Johnson NRR/TSB/ADPR NRC 301 415 3060 dlj@nrc.9ov Carl Schulten NRR/TSB/ADPR NRC 301-415 1192 css 1@nrc. gov Craig Harbuck NRR/TSB/ADPR NRC 301 415 3140 cch@nrc. gov Nanette Gilles NRR/TSB/ADPR NRC 301 415 1180 nvg@nrc. gov Jack Foster NRR/TSB/ADPR NRC 301-415 3647 jwf@nrc. gov Haggalean Weston NRR/TSB/ADPR NRC 301-415 3151 mww0nrc. gov Page 2

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Attachment 1 ATTENDEES LIST NRC/TSTF OWNER'S GROUP MEETING October 1 and 2, 1997 NAME ORGANIZATION ADDRESS PHONE # E Mall 10 Bob Giardina NRR/TSS/ADPR NRC 301 415 3152 BobTjader NRR/TSB/ADPR NRC 301 415 1187 trtenrc. gov i

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Attachment 2  !

TSTF 135 00ESTIONS May 6, 1997 AND RESPONSES May 12e 1997

1. On retyped page 3.3 6 (RTS) Required Action *P.2" should be 'P.1".

Aveed 00 Anknnwho131F 135.

2. For current RTS Function 18, the current Required Actions S and T require the
verification that interlocks are in the required state and the unit be placed in a specified MODE within a required time limit. With the deletion of Function 18, how are these i requirements met? Where in the Bem are these topics discussed?

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anyspA Theissdods a enssed en she fasew4 paswd meetly a presented h Aev.1. Abe, Sasa page 8 3.3 1 I has a few mesaww h she mend perspaph tvis 4 these 6mwiscas'(wwsden se the Tr$ Fwweisne' Operehary. ,

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and she Anlus Ier she a#ened Fwusion(s) are eders which wN (m appropriere) tvehe the shadown to a spec # led Nede k a reededske, seerf odern anake knennea twesene our er nrs amt twas sesk.  :

3. For current RTS Function 20, reactor trip breaker undervoltage and shunt trip rnechanisms in MODES 1 and 2, the current Required Action "U.2.2 Open RTB" requires the reactor trip breaker to be opened within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after MODE 3 is achieved. The replacement Required Actions, S and T, do not include an "Open RTB" requirement. Should these replacement actions include " Place Rod l Control System in a condition incapable of rod withdrawal action", similar to Required Actions C.3 and 1.2. If not, provide justification for the elimination

. of the "Open RTB" re;quirement.

t the Aev. I anden U.2.2 * *Open ATRs,* 4 aseresy NOT AfQUlAfD, shce seen enewN Nede 3, the Appsce6ery or she Fwusion shst 4 monN Anton U 6e enred,4 eded on wwwh Mode J, that heperable Fwwsden wei# shen doet enry 6se Assion C (Rev 11 er sww U), etJch has the *epen ATI'aciden. $sa#acespa, no sharge to 737F 135 troeded

4. On retyped page B 3.3 9 (RTS) ltem f ' Turbine impulse Pressure. P 13, check the ,

sentence structure of the last sentence.

Osaste she endrea s appscable*phrew, oc assion se rode TT7F 135 .

5. On retyped page B 3.310lr and insert 8 (ESFAS) Actions L.1 and L.2 for Functions 1d Safety trQoction Pressurizer Pressure Low and 4d(1) Steam Line isolation Steam Line  ;

Pressure Low the first sentence reads "If the Required Action or associated Completion Time for Condition Lis not met." This sentence should read "If the Requir*d Action or  :

essociated Completion Time for Condition K is not met."

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For ESFAS Function 4d(2) Steam Line isolation Steam Line Pressure Negative Rate -

High, Required Action D_ currently requires the entry into MODES 3 and 4 if an L

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j inoperable channel cannst be placed in trip. The replacement Required Action O I requires the reduction of pressurl er pressure. Provide justification for this change?  !

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7. For ESFAS Functions de Steam Une isoletion High Steam Flow in Two Stoem unos i Coincident with T., Low Low and 4g Steam Une laolation High Steam Flow Coincident {

with T., Low Low, Required Action D currently requires the entry into MODES 3 and ,

4 if an inoperable channel cannot be placed in trip. The replacement R64uired Actions M and N require entry into MODE 3 and the reduction of RCS temperature. Provide justification for this change?

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8. Item 12 of TSTF 135 Traveller addresses the removal of interlocks as separate RTS functions. However, the package also includes the removal of interlocks as separate l

- ESFAS functions. These changes require a justification in the Traveller?  :

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Additional TSTF 135 Questions September 30,1997 i

Meector Prorection System Instrumentation

g. Actions are modified by a Note that changes ' separate condition entry" to a *per channel
  • basis from a *per function' basis. The staff SE for WCAP.10271 approved channel repair ,

and surveillance AOTs for TS required functions. Provide analysis and discussion to confirm  :

that proposed changes are consistent with WCAP 10271 as approved by the staff.

10. RTB and Undervoltage Shunt Trip Functions include a shutdown track action for the Mode 1 & 2 apphcability. The NUREG allows a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> channel repair time and then an additional 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> exit to Mode 3 with an schon to "open RTB' within the next hour. Proposed changes allow 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to repair, then exiting the applicability to Mode 3, then an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to repair with a shutdcwn track to insert rods and disable the Rod Control System from pulkng rode. The "open RT8' adion is deleted and the repair AOT is extended to g6+ hours.

Provide analysis and discussion to confirm that proposed changes are consistent with WCAP 10271 as approved by the staff.

11. NUREG Action D.1.2 requires thermal power to be reduced to equal to or less than 75% RTP (in addition to placing an inoperable channelin trip) to prevent operation of the core radial .

power distributions beyond the design limits. The Bases for D.1.2 state that with one of the $

NIS power range detectors inoperable 1/4 of the radial power distribution monitoring capability is lost. TSTF justification #6 Justifies deleting the requirement to reduce thermal power and states that the STS actions are "too conservative" and parenthetically adds that the trip device of the channel may be inoperable but the indicators are still operable and able -

to monitor QPTR. Provide a safety analysis discussion to support deleting the NUREG i action that is specified because reducing thermal power is necessary due to loss of radial power distribution monitoring capability.

12.~ Provide a OG position on the Robinson ITS version of Footnote (b) to Table 3.3.1.1 1 for i manual trip, RT8s, Shunt Trips and Automatic Trip logic in Modes 3,4, and 5. The.NUREG footnote was changed by replacing "RT8s closed' with "all rods not inserted." This change 2

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13. Reactor Trip System interlock Table Functions are proposed to be moved to the Bases, These proposed changes are not acceptable (Also discussed in item 2 above. STS SRs , 3.3.1.1.g, 3.3.1.1.11 and 3.3.1.1.13 are affected). l
14. Proposed Required Action 8.1 for Manual Reactor Trip addresses the condition of loss of both trains of manual RPS actuation. Provide a safety analysis basis for delaying  :'

entry into LCO 3.0.3 Dy the addition of the proposed action. Include an evaluation of the acceptability of this one hour allowance with the assumptions of WCAP 10271.  :

Provide a safety analysis basis for replacing the NUREG action to open RT8 with insert  !

all rods and make the RCS incapable of rod withdrawal.

  • acen the nras" ossue i Den nehernoon said that TSTF07 MW 1 pm& des e justification for the operettonet herdsh@ the HOG has <

deh resuMHe shot the MTS be evened of the MTas or the underoiteet or shunt tr@ elevices are inoper0We. l The etetf redected than traveler. The TSS stati As concemed that the use of the proposed sewnistrative '

eentroen Sneert tons end meke the md controlsystem incepeNe of md with$ewellis not appropriate for loopereWe reactor tr@ brenaers or undervolteer shunt 115 devices. in ad$tton. the proposal to define o eget:lfled condtton for :he Mies in Modes 3. 4 and 6 that uses etninistrative contmos Ithe status of the non selety MCS Ancepeur of md with&owell and for which there are no operability reevirements does ,

pedale appropriate Smits for e specifiedplant condtion.

15. NUREG Required Action B, for one inoperable manual reactor trip breaker channel not restored to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, includes B.2.2 which specifies "Open

- RT8s." This action is proposed to be replaced with Required Action C.1, " Initiate action to fully insert all rods

  • and Required Action C.2, " Place the Rod Control System in a condition incapable of rod withdrawal " Provide a safety analysis justification fo. this  :

proposed change.

16. The NUREG Actions Note (derived from WCAP 10271) which allows a channel to be bypassed for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to perform surveillance testing is proposed to be applied to new Actions D.1, J.1, L.1, and 0.1. These actions apply upon discovery of failure to meet multiple inoperable channels. Confirm that this proposed change is consistent with WCAP.

10271 as approved by the staff.

17. Justification 6 justifies deletion of D.2.1: however, D.2.1 is retained as D.2. The justification relies mainly on operational convenience as the basis for changes to actions for power range neutron flux. Provide revised justification that includes safety analysis i discussion for the proposed deletion of required actions D.1.2 and D.2.2.
18. NUREG Required Action J for two inoperable source range neutron monitoring channels includes J.1 which specifies "Open RTBs." This action is proposed to be replaced with

" Verify all rods are fully inserted and not capable of rod withdrawal." Provide a refety analysis justification for this proposed change.

19. NUREG Required Action K for one inoperable source range neutron monitoring channel not restored to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, includes K.2 which specifies *Open '

RTBs." This action is proposed to be replaced with Required action 1.1, " initiate action to fully insert all rods

  • and Required Action 1,2, " Place the Rod Control System in a condition incapable of rod withdrawal." Provide a safety analysis justification for this proposed change.

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20. NUREG Required Action O includes a Note that allows a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />'STl bypass bef:re acti:n requirements must be met. This allowance is deleted from the proposed Required Action M without justification. .
21. NUREG Notes to required actions for or.e inoperable reactor trip breaker in Modes 1 and 2 are proposed to be changed by the addition of the phrase "provided the RTB is bypassed with an OPERABLE RTBD.* Provide a safety analysis justification for this proposed change.
22. Propor,ed Required Action U.1 for reactor trip breakers, trip mechanisms and trip logics in Modes 3,.4 and 5 addresses the condition of loss of both trains of actuation. Provide a safety analysis basis for delaying entry into LCO 3.0.3 by the proposed addition of U.1. Include an evaluation of the acceptability of this one hour allowance with WCAP.

10271. Provide additional safety analysis basis for tspiccing NUREG action to open RTB with insert all rods and make the RCS incapable of rod withdrawal.

23. NUREG Required Action C, for one inoperable reactor trip breaker train (or one mechanism per RTB) not restored to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, includes C. 2 which specifies "Open RTBs." This action is proposed to be replaced with Required Action V.1, " initiate action to fully insert all rods" and Required Action V.2, " Place the Rod Control System in a condition incapable of rod withdrawal." Provide a safety analysis justification for this proposed change.

FSFAS Instrumentation

24. Actions arg modified by a Note that changes
  • separate condition entry
  • to a *per channe!"

basis from a *per function

  • basis. The staff SE for WCAP 10271 approved channel repair and surveillance AOTs for TS required functions. Provide analysis and discussion to confirm that proposed changes are consistent with WCAP 10271 as approved by the staff.
25. Proposed Required Action B.1 for Manual SI, Containment Spray, Phase B lsolation and Steam Une isolation functions addresses the condition of loss of both trains of manual ESFAS initiation. Provide additional safety analysis basis for delaying entry into LCO 3.0.3 by the proposed addition of Action B.1. Include an evaluation of the applicability of this one hour allowance to WCAP 10271. Provide additional safety analysis basis for replacing NUREG action to open RTB with insert all rods and make the RCS incapable of rod withdrawal.
26. TSTF 135 proposes to apply NUREG Actions Note (der'ved from WCAP 10271) which allows a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> bypass to perform surveillance testing to the new Actions D.1, F.1, G.1, K.1, M 1,0.1, and R.I. These actions apply upon discovery of f ailure to meet multiple inoperable channels. Confirm that this proposed change is consistent with WCAP 10271 as approved by the staff.
27. Proposed conditions for low steam line pressure actuation of Safety injection (Table 3.3.21, Function 1.e(1)) specifies condition F with alternate (condition K). Explain the intended application of using attemate condition K. Explain the application of condu,on K to other table functions with 3,2 or 1 required channel as specified in Table 3.3.21,
28. Proposed condition M replaces NUREG 1431 condition D for Table 3.3.21 funct!ons related to steam line isolations (Functions 1.f.1.g, 4.e anc 4 0). The current

! 4 L:::::: ':: = -.____: -- -

requirements require exiting the modo cf applicability 13 Mode 4. Proposed c;nGati:n N.2 requires exiting the applicability to ' reduce RCS temperature to below P.12.*

Provide documentation that P.12 has a specific temperature associated with the interlock which is generic to the Westinghouse design. Explain why this remedial action is an appropriate limit.

29. Explain the use of condition K for pressuriser pressure low actuation of SI (Table 3.3.2 1, Function 1.d). The current requirements require exiting the tr. ode of applicability to Mode 4. Proposed condition L.2 requires exiting the opplicability to
  • reduce pressurizer pressure below P 11." Provide documentation that P 11 has a specific pressure associated with the interlock which is generic to the Westinghouse design. Explain why this femedial action is an appropriate limit.
30. Proposed condition H replaces condition E for manualinitiation of steam line Isolatlun and for low suction pressure auxiliary feedwater initletion (Table 3.3.21, functions 4.a.

and 6.h, respectfully) which changes the action from

. trip within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

  • to " restore channel to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.* The justifications do not provide analysis or discussion that confirms that this proposed change is consistent with WCAP.10271 as approved by the staff.

s 5

.v. .

  1. . %.e ,-s m w. e. , p -

.%,y, %g,, ,w,

Attachment 3 L

~

1he following list is of new travelers received by NRC at the 10/12/97 joint NRC/TSTF Gwer's Group meeting from the TSTF Deer's Group. Complete copies of the travelers may be obtained through the Public Document Room.

- TSTf 65. Rev. 1 Use of generic titles for utility positions '

TSTF 87, Rev. 2 Revise "RTBs open* 8 *CRDM de energized

  • Actions to
  • incapable  !

of rod withdrawal * ,

i TSTF 93, Rev. 3 Change the frequency of pressurizer heater testing from 92 daysto(18) months  :

TSTF 110. Rev. 2 Delete SR frequencies based on inoperable alarus TSTF 127. Rev. 1 Decrease frequency to 92 days for CHI and CEA Deviation Circuit functional Test i

TSTF 128. Rev. 1 Revise TSB Description s

P N O 7f W ' ^

  • ND - - - - - - -" %W6 99PE '
  • UN I*#- 'O C- 8 4f--- - # '
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