ML20116E532

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Provides Info Re 18 Month Surveillances Which Have Entered or May Enter 25% Grace Period Due to Current Unit 2 Extended Operating Cycle
ML20116E532
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 10/30/1992
From: Beck G
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9211090227
Download: ML20116E532 (15)
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PIIILADELPillA ELECTRIC COMPANY NUCLE /.2 GROUP HEADQUARTERS l 955-65 CHESTERBROOK BLVD. I WAYNE, PA 19087 5691 al$) 640Roo October 30, 1992 Docket Hos. 50-352 l NucuiAR $LRVICES DLPARTMENT 50-353 License Nos. NPF-39 NPF-85 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Subject:

Limcrick Generating Station, Units 1 and 2 18 Month Surveillances Which Have Entered or May Enter the 25% Grace Period Due to the Current Unit 2 Extended operating cycle Gentlemen:

By letters dated September 1, 1992 and October 15, 1992, Philadelphia Electric Company (PEco) submitted Technical Specifications Change Request (TSCR) Nos. 92-02-0 and 92-03-0, respectively, in accordance with 10 CFR 50.90, requesting an amendment to the Technical Specifications (TS) (i.e.,

Appendix A) of Operating License Nos. NPF-39 and NPF-85. These submittals requested changes to TS surveillcnce intervals to facilitate a change in the Limerick Generating Station (LGS), Units 1 and 2, refueling cycles from 18 months to 24 months. The 24 month refueling cycle will require a change from the current 18 month TS surveillance testing interval (i.e. , a maximum of 22.5 months accounting for the allowable grace period) to a 24 month testing interval (i.e. , a maximum of 30 months accounting for the allowable grace period) . These proposed TS changes were evaluated in accordance with the guidance provided in NRC Generic Letter (GL) No. 91-04, " Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle," dated April 2, 1991. As a result of discussions with NRC personnel on September 22, 1992, the following information is provided regarding the Unit 2 and common plant TS Surveillance Requirements (SRs) that may enter the 25% grace period due to the current Unit 2 extended operating cycle.

The attachment to this letter provides the TS FR section number and *-b a brief description of those 18 month TS SRs that passed our acceptance criteria for a change to 24 months, and entered - the 25% grace period allowed by TS Section 4.0.2 as a result of the current LGS Unit 2 extended operating cycle. (Note: this acceptance criteria is described subsequently

, in this letter). Furthermore, certain 18 month TS SRs did not pass our i

acceptance criteria for a change to 24 months. As a result, these 18 month SRs were not included in the TSCRs, and therefore, will remain at the current 18 month testing interval. of those 18 month TS SRs not included i in the TSCRs, some entered th 2 25% grace period. These TS SRs are 9211090227 921030 PDR ADOCK 05000352 L

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4 U. S. Iluclear Regulatory Commission October 30, 1992 Document Control Desk Page 2 i

indicated in the attachment by the wording "(18 months)" next to the specified SR. In addition, the attachment conservatively lists the TS SEs that are acheduled to be performed prior to the second refueling outage for IAS , Unit 2, currently scheduled to begin on January 23, 1993. These TS SRs may or may not be parformed within the current TS required 18 month surveillance testing interval (i.e., prior to entering the grace period) i

depending on the current work schedule and whether the SRs are outage or j non-outage related. As a result, not all of the TS SRs identified in the attachment will enter the 25% grace period. (11ote
the " Group" column in '

I the attachment is for information purposes and specifies the " group" within TSCR lio . 92-02-0 or 92-03-0 under which the individual TS SRs were evaluated for a change from 18 months to 24 months.)

The TS SRs listed in the attachment have surveillance interval end dates that fall at various times between July 1992 through January 1993.

Accordingly, the grace periods for these SRs may overlap, resulting in the possibility that a number of SRs will be in the grace period at the same time. However, since the surveillance tests will actually be performed at various times, not all the TS SRs on the attached list will be in their associated grace period simultaneously. We intend to complete all TS SRs prior to exceeding their associated grace period. i As indicated previously, these TS SRs were evaluated for a change to a maximum of 30 months (i.e., accounting fer the allowable grace period) in TSCR Nos. 92-02-0 and 92-03-0. Our evaluations concluded that the proposed changes to a 24 month testing interval do not involve an unreviewed safety question. In addition, no instrument setpoints needed to be changed in order to extend the surveillance interval to a maximum of 30 months. If the instrumentation did not pass our acceptance criteria, i.e., the projected 30 month drift value resulting from a drift analysis i based on historical data was not within the current bounding analysis limits, or a change to 24 months could not be justified on any alternative basis, such as system redundancy or more frequent testing, the afft:ted SR will remain at the current 18 month testing interval. As a result of the above discussion, we have concluded that the_various TS SRs which may be in grace at any point in time is acceptable.

Additionally, for information purposes, below is a sample listing of .

TS SRs which were eva'uated for a change to 24 months but did not pass our ]

acceptance criteria, and thereforc, Will remain at the carrent 18 month testing interval. These TS SRs were performed within the current TS '

required 18 month testing interval (i.e., prior to entering the allowable 25% grace period).

l Technical Specification Section/Descrintion 4.3.7.8.2.c; Toxic Gas channel-calibration 4.6.2.1.c.3 ; Suppression Pool Level / Temperature instrument calibration Table 4.3,3.1-1 ltem 3.d; High Pressure Coolant Injection - High suppression Pool Level instrument calibration 1

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U ., S . Nuclear hogulatory Commission October 30, 1992

. Document Control Desk- Page 3-Also, below is a sample listing of TS SRs which passed our acceptance criteria for a change to 24 months, but were nevertheless performed within the current TS required 18 month testing interval.

l 1echnical Specification Seqtion/pescription 4.4. 3.2.3.b; High/ Low Pressure Interface leakage instrument calibration 4.5.1.c.4; Core Spray Differential Pressure instrument calibration

4. 6. 5.3.b.1; Standby Gas Treatment System High Ef ficiency Particulate Air (HEPA) filter / charcoal filter testing 4.7.1.2.b.1; Emergency Service Water valve actuation on pump start 4.".2.c.1; Control Room Er?rgency Fresh Air System HEPA filter / charcoal filter testing 4.7.3.c.4; Reactor Core Isolation Cooling (RCIC) Keep-Filled instrumentation calibration Table 4.3.2.1-1 Item 1.g; Main Steam Line Tunnel high temperature calibration Table 4.3.3.1-1 Item 2.d; Low Pressure Coolant Injection valve differential pressure calibration Table 4. 3.5.1-1 Iteu c; RCIC - Low Condensate Storage Tank Level instrument calibration Table 4.3.7.1-1 Item 1; Control Room Fresh Air Supply' Radiation Monitor calibration Table 4.3.7.2-1-Item 1.a.6; Seismic Monitoring sensor calibration Table 4.3.7.4-1 Item 8; Remote Shutdown Panel - Residual Heat Removal flow instrument calibration -;

Table 4.3.7.5-1 Item'12; Accident Monitoring Instrumentation - North Stack Wide Range Radiation Monitor calibration If you have any questions, please do not hesitate to contact us.

Very truly yours, G. J.

f'fd ck, Manager 4/ !$l .

Licensing Section Attachment cc:- T. T. Martin, Administrator, Region I, USNRC w/ attachment T. J. Kenny, USNRC Senior Resident Inspector,. LGS w/ attachment d

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I ATTACHMENT Limerick Generating Station, Units 1 and 2 Docket Nos. 50-352 50-353  ;

License Nos. NFF-39 ,

NPF-85 "18 Month Surveillances Which Have Entered or May Enter the 25% Grace Period Due to the Current Unit 2 Extendad Operating Cycle" F

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PAGE: 10 TEC A CAL SPECIFICATION DESCRIPTION . GROUP 14.3.4.2.1-1 ITEM 2 EOC RPT MTCV CLOSURE CAL SPRP(6) 14.3.5.1 1 ITEM A RCIC LEVEL 2 Wit CAL $PRP(2) 14.3.5.1 1 11EM B RC!C LEVEL 8 Wit CAL SPRP(2) 14.3.5.1 1 11EM D RCIC MANUAL INIflATION- MAN!

14.3.6-1 ITEM 7 RX MODb SW11CH POslif0N FUNC MODE i

14.3.6 1 liEM 5.A SDV W1R LEVEL HI CAL SPRP(7) 14.3.7.1 1 ITER 2. A.1 SPENT FUEL POOL CRil. MON. SPRP(8)

CAL 14.3.7.1 1 ITE M 3 RE',W RAD MOW CAL SPRP(8) -

14.3.7.12 1 11EM 4.h NOBLE GAS ACT:VITY MONITOR SPRP(8)

CAL 14.3.7.2 1 11EM 4 SEIS4]C MONITORING ANALYZER SPRP(4)

CAL T4.3.7.41 ITEM 1 REM 01E S/D RX PRESS CAL SPRP(4', :r 14.3.7.4 1 11EM 10 RSP RHR HTX S/W PRESS CAL SPRP(4) 14.3.7.4-1 11EM 11 RSP RCIC FLOW CAL $PRP(4) 14.3.7.4 1 ITEM 12 RSP RCIC TURB SPEED CAL SPRP(4) g 14.3.7.4-1 ITEM 14 RSP CST LEVEL CAL. .SPRP(4) I

~

ni 14.3.7.4 1 11EM 15 RHR HTX 8/P VLV POSITION ~SPRP(4)

IND. CAL i .-.

74.3.7.4 1 11EM 16 RSP RCIC TURB TRIPPED,1ND. SPRP(4)'

CAL T4.3,7.4 1 ITEM 17 RSP RCIC TURB BRG Oll PRESE SPRP(4)

LOW IND CAL :t

'14.3,7.4 1 ITEM 18 RSP RCIC LP BRG OIL TEMP HI SPRP(4)

!MO. CAL' ,

.: _. . . . - . . - . . - . , . = - -  :. . .- ,.

PACE: 11 itCHNICAL SkECIFICAtlDN DESCRIPTION GROUP 14.3.7.4 1 11tM 19 RSP RHR HTX DISC. LINE Mt SPRP(8)

RAD IND. CAL 14.3.7.4 1 If[M 2 RSP RX LEVIL CAL FERP(4) 14.3.7,4 1 11tM 4 RSP S/P t[ VEL CAL SPRP(4) f4.3.7.4 1 litM 5 RSP S/P W1R f(MP CAL SPRP(4) 14.3.7.4 1 11EM 6 RSP D/W PRESSUR[ CAL SPRP(4) 14.3.7.4-1 IILM 7 RSP D/W TEMP CAL SPRP(4) 14.3.7.5 1 litM 1 ACCIDENT MONITORING INST RX SPRe(4)

PRESS CAL T4.3.7.5 1 litM 10 A/M INSTR SRV VLV POstfl0N CFRP(4) l*0. CAL 14.3.7.5-1 11tM 11 A/M INSTR P/C POST LOCA RAD SFRP(8)

MON CAL 14.3.7.5 1 litM i3 A/M INSTR NEUTRON FLUX CAL SPRP(4) 14.3.7.5-1 11EM 2 A/M INSTR - RX LEVEL CAL SPRP(4) 14.3.7.5 1 11tM 3 A/M INST S/P WiR LEVIL CAL SPRP(4) 14.3.7.5 1 11[M 5 A/M INSTR S/P AIR TEMP CAL SPRP(4) -

14.3.7 5-1 11EM 6 A/M INSTR P/C PRtS> JAL SPRP(4)

T4.3.7,5 1 11tM 7 A/M thSTR D/W AIR TEMP CAL SPRP(4) 14.3.9.1 1 11EM 1 F/W MAIN TURB LEVEL 8 W1R CAL SPRP(9)

(INS OF REPORT)

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