ML20235K845
| ML20235K845 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 02/03/1989 |
| From: | Papanic G YANKEE ATOMIC ELECTRIC CO. |
| To: | Fairtile M Office of Nuclear Reactor Regulation |
| References | |
| BYR-89-20, IEB-86-094, IEB-86-94, NUDOCS 8902270264 | |
| Download: ML20235K845 (22) | |
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% ^ YANKEEATOMIC ELECTRIC COMPANY
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, YANKEE 580 Main Street, Bolton, Massachusetts 01740-1398 f.
February 3, 1989 BYR 89-20 l
United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attention: Mr. Morton B. Fairtile, Project Manager Project Directorate I-3 Division of Reactor Projects I/II
References:
(a) License No. DPR-3 (Docket No. 50-29)
(b) Letter, YAEC to NRC (FYR 88-01), dated January 4, 1988 (c) Letter, NRC to YAEC (NYR 87-142), dated July 16, 1987
Subject:
Systematic Evaluation Program (SEP) Commitments
Dear Sir:
This letter is intended to inform you of the status of our SEP commitments. These commitments have been mutually agreed upon and are described in detail in the various SEP topical safety evaluations. We were requested to submit our schedule for the work associated with these commitments and to inform you when each has been completed.
The matrix enclosed with this letter provides both a summary status and schedule for all SEP commitments. More than 60 percent of these have already been finished. Each remaining commitment has been prioritized and the work needed to fulfill the commitment has been scheduled.
Work has recently been completed at our refueling shutdown on seismic supports for Safe Shutdown System (SSS) piping inside containment. Also, I final engineering has commenced on structural upgrades to the Primary i Auxiliary Building (PAB) and the Diesel Generator Building (DGB) scheduled for this year.
We have previously informed the staff, on i~ arch 9, 1987, that the DGB was not grt of the SSS scope. Yankee has reconsidered this classification. We now intend to include part of the DGB within the SSS scope. This will allow us greater flexibility in the future and avoid having to relocate SSS conduit as previously planned. This change in classification has no effect on our SEP commitments since we had already agreed to seismic upgrades to the DGB (see Item No. 10 in the attached matrix). The seismic modifications for the DGB are based on NRC spectra exclusively. i l
I 8902270264 890203 DR ADOCK 0500 9 [0
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United States Nuclear Regulatory Commission February 3, 1989 Attention: Document Control Desk Page 2 A number of commitments have been completed recently for SEP Topic III-6. A summary of their resolution is presented below. The item numbers match with the attached matrix.
Item No. 15 A physical examination of the PAB masonry walls was performed to determine the condition of the steel strap anchors. These straps connect the concrete masonry exterior walls to the steel framework of the building. The investigation confirmed that the strap anchors are solidly grouted, thereby conforming to the assumptions made in the various seismic and tornado analyses performed during SEP.
Item No. 37 New Amplified Response Spectra (ARS) have been generated for the Vapor Container using the soil springs model approved by the staff during their SEP review. NRC site-specific ground spectra were used as input.
These ARS were generated by Cygna Energy Services in conformance with their Quality Assurance Program. Their work was checked and independently reviewed by their senior level engineers. It has also been reviewed in detail by Yankee mechanical and structural engineers.
The spectra are being used as input for seismic analysis of piping inside containment. Actual piping modifications will be made only after a 10CFR50.59 safety evaluation has been performed.
Item No. 38 The behavior of the Neutron Shield Tank (NST) under seismic load has been evaluated. Our analysis report was submitted to the staff via Reference (b). The analysis demonstrates that the NST would neither slide nor uplift under NRC spectrum seismic loads; consequently, no plant modifications are needed to inhibit these motions.
This analysis was performed by Cygna Energy Services in conformance with their Quality Assurance Program. Their work was independently reviewed by their senior level engineers. It has also been reviewed in detail by l' Yankee mechanical and structural engineers.
The obligations relative to the scope, analysis criteria, and load combinations specified in the staff's Topic III-6 safety evaluation, Reference (c), were fulfilled in performing this work.
Item No. 44 In the future, modifications to existing Safe Shutdown System (SSS) piping and new SSS piping will be designed to our Seismic Re-Evaluation and Retrofit Criteria Document, DC-1, using NRC spectra.
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s2 . . s United States Nuclear Regulatory Commission February 3, 1989 Attention: Document Control Desk Page 3 Item No. 50 Yankee has withdrawn its proposal to use U-bolts for axial restraint of SSS piping. Conventional support configurations, consistent with DC-1, will be used instead. As a result,'our commitment to add these U-bolts to our ISI program is unnecessary.
Item No. 52 The concerns identified in IE Information Notice 86-94 regarding 1/2 inch diameter Hilti Bolts have been addressed. All applications of the use of these bolts for safety-related components were reviewed. Existing bolts have, at least, the required safety factor of 4.0, using the lower allowables published in the bulletin. For future applications of 1/2 inch Hilti Bolts we will use the new design allowables published by Hilti.
Item No. 55 Bracing has been added to the legs of the component cooling surge tank for seismic stability. NRC spectra were used. Yankee engineers' designed the modifications in conformance with our Quality Assurance Program.
Both an independent review and a 10CFR50.59 safety evaluation were performed prior to implementation.
In accordance with your previous request, we will advise you periodically.
as each of the remaining SEP commitments is fulfilled.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY P
G. Pa anic, J Senior Project Licensing Engineer GP/0165v Attachment cc: USNRC Region I USNRC Resident Inspector, YNPS w________-___-__- ---______________--_ - _- _____ ____-__ - .__ _ _ _ _ _ _ _ _ _ _ _ _ _ - . . - _ - -
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., XANJ.EE NUCLEAR POWER STATION n
So==-ry of Systematic Evaluation Program Commitments January 1989~
SEP'(1). Item I .__Inpic ' Reference Documents (2) Commitment S ry Status (3) Humhnr II-2. A - Ref. (11)- Institute snow removal RESDINED: No 1-Ref.:(14) procedures whenever snow further-action
'Ref. (71); loads approach 40 psf.- required..
Resolution made through Topic III-7.B.-
'II-2.C Ref. (15) Use CHI /Q values presented REEOLVED: -These' 2' Ref. (16) in Ref. (15) for all values are being Ref. (67) accident radiological used.
consequence calculations.
II-3.B.1 Ref. (1), Para. 4.1.4 Improve the drainage at CDMELEIED: Plant 3 Ref..(35) the south. fence-(into. Alteration 85-009.
Wheeler Brook) to prevent local site flooding.
'II-3.B.1 Ref. (1), Para. 4.1.5 Install roof scuppers to COMELETED: Plant 4 Ref. (2), Para ~. 4.1.1 prevent flooding of the Alteration 83-31.
- Ref. (4) Turbine Building roof.
II-3.0 Ref. (1), Para. 4.1.4 Install a Dedicated Safe COMPLETED: EDCRs 5 Ref. (36) Shutdown System (SSS) for 84-308, 84-309 III-2 Ref. (1), Para. 4.5 primary and secondary and 84-310.
Ref. (10) make-up water in the III-3.A Ref. (1), Para. 4.6.1 event a flood, tornado, or III-6 Ref. (1), Para. 4.11 earthquake disables other VII-3 Ref. (1), Para. 4.19.2 normal and emergency systems.
II-4.P Ref. (1), Para. 4.3.2 Install a steel liner in CDMELETED: 6 Ref. (37) the spent fuel pool. EDCR 78-12G.
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SEP (1) ,
Item i Topic Reference Documents (2) Commitment Sn==ary Status (3) Number III-2 Ref. (2), Para. 2.3 Upgrade the ultimate COMPLETED: 7 Ref. (10) capacity of the Cable .
EDCR 86-305 Ref. (13) Spreading Room to sustain a Ref. (32) 186 mph tornado and a '
196 mph straight wind.
III-2 Ref. (2), Para. 2.3 Modify the Diesel Generator Scheduled for- 8 Ref. (10) Building (DGB) Cubicle 1989 and 1990. i Ref. (31) No. 3 west block wall to Ref. (61) sustain a 121 mph tornado Ref. (62) and 134 mph wind loads.
III-2 *Ref. (10), TER p. 14 Evaluate the DGB roof deck COMELETED: No '9 Ref. (32) for a 121 mph tornado modifications Ref. (62) and 134 mph wind loads. required.
This commitment was Modify the deck if made to NRC during necessary.
a meeting on 2/6/86.
III-2 'Ref. (1), Para. 4.5 Modify the DGB structural Scheduled for 10 Ref. (62) frame to sustain a 134 mph 1989 and 1990.
III-6 Ref. (1), Para. 4.11.1 wind, 121 mph tornado, and i Ref. (3), Item 5 seismic loads. !
Ref. (9), Para. 4.3.9 Revise two existing Ref. (34), connections to decouple the
. Question C.4.a.ii DGB and PAB in the Ref. (63) horizontal direction.
III-2 Ref. (2), Para. 2.3 Modify the PAB upper level Schedul'ed for 11 Ref. (10) west block wall to sustain 1989 and 1990.
Ref. (13) a 121 mph tornado and
.Ref.'(61) 134 mph wind loads.
Ref. (62)
III-2 Ref. (10) Evaluate the connections Scheduled for 12 Ref. (13) between the roof deck and 1989 and 1990.
Ref. (32) the PAB structural steel, Ref. (61) between Column Lines 6-8.
Upgrade, if necessary, to equal the uplift capacity of the roof deck.
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SEP.(1) ,
Item Topic' Reference Documents (2) Commitment Summary S taluR__(3 ) Number 1
III-7.B Ref. (2), Para. 2.6 Modify the lower level Scheduled for. 13- I Ref. (11) roof of the PAB to sustain 1989 and 1990. [
Ref. (56). increased snow loads of up Ref. (64) to 125 psf.
III-2 Ref. (1), Para. 4.5 Modify SSS related block Partially resolved 14 Ref. (2), Para. 2.3 walls in the PAB and pipe via EDCR 86-305.
Ref. (10) tunnels to sustain various Remainder of work Ref. (39) wind, tornado, and NRC scheduled for 1989 Ref. (62) spectrum seismic loads, and 1990.
III-6 Ref. (1), Para. 4.11.1 Add two structural steel Ref. (3), Item 11 members to support the Re'f. (9), Para. 4.3.12 PAB upper level north Ref. (38) block wall.
III-6 Ref. (3), Item 12 Verify that strap anchors COMPLETED: Anchors 15 Ref. (9), Para. 4.3.4 in the PAB north block are solidly grouted.
Ref. (34), Question C.7 walls are solidly grouted.
Ref. (81) If they are not, take corrective action.
III-2 Ref. (1), Para. 4.5 Modify the PAB structural Scheduled for 16 III-6 Ref. (1), Para 4.11.1 steel frame to sustain a 1989 and 1990.
Ref. (3), Item 6 165 mph tornado, NRC Ref. (9), Para. 4.3.4 spectrum seismic loads, III-7.B Ref. (11) and 125 psf snow loads.
Ref. (17) Analyze new and existing Ref. (40) steel embedments using Ref. (41) ACI 349-76, Appendix B.
Ref. (62) Use a safety factor of Ref. (64) 4 for Hilti bolts.
III-2 Ref. (1), Para. 4.5 Modify the SSS related Partially resolved 17 Ref. (2), Para. 2.3 block walls in the Turbine via EDCR 84-317.
Ref. (10) Building to sustain Remainder of work Ref. (38) various wind, tornado, scheduled for 1990.
III-6 Ref. (1), Para. 4.11.1 ond NRC or twice YCS Ref. (3), Item 11 spectrum seismic loads.
Ref. (9), Para. 4.3.12 III-6 Ref. (1), Para. 4.11.1 Modify the Turbine CDELEIED: 18 Ref. (9), Para. 4.3.7 Building structural steel EDCR 83-35.
Ref. (34), and concrete frame to Questions B.8 and C.3 sustain NRC spectrum seismic loads.
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SEP (1) , Item
__Inpic Eeference Documents (2) Commitment Summary Status (3) Humhnr III-7.B Ref. (2), Para. 2.6 Modify the Heating Boiler Scheduled for 19 Ref. (11) Room roof to sustain 1989 and 1990.
Ref. (56) increased snow loads of Ref. (64) up to 125 psf.
III-2 Ref. (1), Para. 4.5 Modify supports for Scheduled for 20 l Ref. (10), Para. 5.0 exposed main steam and 1991. !
Ref. (13) feedwater (MS/FW) piping to Ref. (61) sustain a 178 mph tornado III-6 Ref. (1), Para. 4.11.2 and NRC spectrum seismic Ref. (2), Para. 2.3 loads. Load combinations Ref. (3), Item 1 are defined in the Seicmic Ref. (9), Para. 4.3.13 Re-evaluation and Retrofit Ref. (33) Criteria Document (DC-1)
III-7.B Ref. (11) and Ref. (11).
III-2 Ref. (1), Para. 4.5 Modify the main steam Scheduled for 21 Ref. (2), Para. 2.3 and feedwater support 1991.
Ref. (10), Para. 5.0 structure, including the Ref. (32) NRV enclosure to sustain III-6 Ref. (1), Para. 4.11.1 a 178 mph tornado and Ref. (3), Item 1 NRC spectrum seismic Ref. (9), Para. 4.3.13 loads. Load combinations Ref. (17) are defined in DC-1.
Ref. (33)
III-7-B Ref. (11)
III-7.B Ref. (11) Evaluate all new and Scheduled for 22 Ref. (40) existing structural steel 1991.
Ref. (64) tension members, and members subject to axial tension and bending in the MS/FW support structure using the AISC Code, 8th Edition (Para. 1.14.2.2 and 1.6) and DC-1.
III-7.B Ref. (11) Analyze new and existing Scheduled for 23 Ref. (40) beam-to-wall connections 1991.
Ref. (64) for the MS/FW support structure using Appendix B i of ACI 349-76. l 1
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SEP (1) Item i: ._ lop.ic_._ ' Reference Documents (2) Commitment S - ary Status (3) Eumhar- l III-2 This commitment was
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Evaluate the exposed Scheduled for 24 made to NRC in a _ electrical emergency feed 1991.
meeting on 2/6/86. discharge piping and the charging cross-connect-to-main feed piping for 178 mph wind and 163 mph tornado loads-(ultimate capacity). Modify supports if necessary.
III-2 This commitment was Evaluate the containment Scheduled for 25 made to NRC in a sump suction (recirculation 1991.
meeting on'2/6/86. line) from the bottom of the Vapor Container (VC) to the upper level PAB-for 135 mph wind and 120 mph tornado loads (ultimate capacity).
Modify supports if necessary.
III-3.C Ref. (1), Para. 4.7.1 Maintain copies of FERC RESQLVED: These 26
- Ref. (4) inspection reports of reports are being Harriman and Sherman Dams submitted to and for information purposes. retained by the plant.
III-3.0 Ref. (1), Para. 4.7.2 Perform in-service RESOLVED: ISI is Ref. (6) inspection (ISI) of plant now being performed 27
- Ref. (43) water control structures using Plant Ref. (66) associated with Emergency Procedure OP-4573.
Cooling Water Systems This has been revised and flood protection. to-include tanks used as the ultimate heat sink, roof scuppers, and divertments.
III-5.A Ref. (2), Para. 2.4 Include in the ISI Program RESOLVED: .These 28 Ref. (12) two welds on each main welds are included Ref. (46) steam line near the top of in Plant Procedure Ref. (50) the steam generators. OP-4574.
Ref. (65) Examine these welds once every ten years.
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. . -4 SEP,(1)
- Item
'Toole- Reference Documents (2) Commitment So==ary Status (3) Number
'III-5.'A 29 Ref. (2), Para. 2.4 Include in the ISI Program RES.QLYED: These Ref. (44) four welds on the No. 2 welds are included Ref. (45) steam generator main steam in Plant Procedure
- piping expansion loop OP-4574.
(located near Blister 12E).
Examine these welds every refueling outage.
III-5.A Ref. (2), Para. 2.4 Include in plant procedure RESOLVED: Plant. 30
-Ref. (12) the' requirement for Procedure OP-4232 Ref. (47) periodic visual has been revised Ref. (65) inspection of the five- to include these inch main coolant loop requirements.
cross-over piping. Also, inspect it whenever an unidentified main coolant leak is detected.
III-5.A Ref. (2), Para. 2.4 Modify or add pipe supports Scheduled for 1990. 31 Ref. (12) on the Loops 2 and 4 steam Ref. (48) generator blowdown lines, Ref. (49) where these are adjacent Ref. (50) to each other, to sustain Ref. (65) jet impingement loads due to pipe break.
III-5.B Ref. (1), Para. 4.10.1 Include in the ISI Program RESOLVED: These 32
- Ref. (5) one weld on the outlet of welds are included Ref. (51) each main steam nonreturn .in Plant Procedure valve. OP-4574.
III-5.B Ref. (1), Para. 4.10.2 Install a barrier on the COMPLETED: 33 Ref. (2), Para. 4.3.2 Switchgear Room wall to EDCR 84-317.
- Ref. (7) protect against a break Ref. (51) in the No. 2 feedwater heater extraction steam line.
III-6 Ref. (9), Para. 4.3.6 Evaluate the stresses in Scheduled for 34 Ref. (34), the VC shell at the main 1991.
Questions C.I.d steam and feedwater piping and 0.1.h penetrations under NRC III-7.B Ref. (11) spectrum seismic loads.
Ref. (64) Modify pipe supports if ,
l necessary.
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' Item
.;-Topic- Reference Documents (2) Commitment Sr-- ry . Status (3) Number III-6' Ref. (1), Para. 4.11.1 Modify the Reactor Support- COMPLETED: 35:
Ref. (9), Para. 4.3.5 Structure.(RSS) columns.and EDCR80-24.
Ref. (68) .
footings to sustain NRC spectrum seismic loads.
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-III-6 Ref. (3), Item 17 Revise the Seismic Resolution in 36
-Ref. (9), Para. 4.3.3 Re-Evaluation and Retrofit progress.
Criteria Document (DC-1) Scheduled for 1989.-
to' delete reference to 20 KSF soil ultimate s bearing capacity for the' RSS and VC.
III Ref. (3), Item 16 Generate new in-structure COMELETED: New 37 Ref.-(9), Para. 4.3.6 ARS and relative seismic ARS have been Ref. (78) displacements for the VC generated and verified and RSS using the latest by YAEC.
soil spring data. Use these ARS in future SSS piping analyses.
III-6 Ref. (3),. Item 8 Demonstrate that the RPV/ COMPLETED: Analysis 38 Bef. (9) Para. 4.5.2 NST will not slide or has been submitted -
Ref. (34), uplift under NRC spectrum to the NRC which Question F.2.b seismic loads, or make a verifies that Ref. (52) plant modification to sliding and uplift Ref.'(53) insure acceptable seismic would not occur. No response. further action required.
III-6 - Ref. (9), Para. 4.5.2 Conduct a plant inspection COMELEIED: 39 Ref. (34), of the Neutron Shield Tank PDCR 87-005.
Question F.2.b (NST) support ring and This examination Ref. (42) concrete ledge. was performed Ref. (53) during the 1987 refueling outage.
III-6 Modify the bracing of the Scheduled for 40 reactor missile shield and 1991.
removable cable bridges to sustain NRC spectrum seismic loads.
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5-SEP (1) , Item Topic' ' Reference Documents (2)' commitment Si-- rv Status (3') Number
.III-6 J 'Ref. (9), Para. 4.5 Install lateral supports COMELEIED: 41
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Ref. (68) (snubbers) on the steam EDCR 80-26.
generators to' sustain NRC spectrum seismic loads..
III-6 -Ref. (3), Item 9 Resolve the issue of Resolution in 42 Ref. (9), Para. 4.5.2 potential seismically progress.
Ref. (34),. . Induced uplift on the Scheduled for 1990.
Question D.20.c steam generator support legs using one'of two' methodologies found acceptable to the NRC.
III Ref. (1), Para. 4.11.1 Modify and/or add supports Partially resolved 43 Ref. (3), Items 2 and 18 for all large and small. via EDCRs 82-27 Ref. (9),. Para. 4.4 bore ~(SSS) piping inside and 84-319.
Ref. (34), containment to sustain Completion of Questions D.27 and D.38 NRC spectrum seismic loads. work scheduled for 1988 and 1990.
III-6 Ref. (3), Item 19
. Future major modifications' REED.1YED: YAEC. 44 Ref. (9), Para. 4.4.1.1 to existing SSS piping and will use NRC spectra new SSS piping systems and DC-1 criteria will be designed to the for any future requirements of DC-1 -modifications to using NRC spectrum SSS piping.
seismic loads.
-III-6 Ref. (54) Verify the accuracy of all COMELEIED: All 45 Ref. (70) 12 small bore SSS piping affected drawings This commitment was isometric drawings produced have been checked made to NRC in a by Impe11 using Cygna 100 crcent technical review sketches, and revised as meeting of 1/6-9/87. necessary.
'III-6 Ref. (3), Item 15 Evaluate the effect of Scheduled for 1988, 46 Ref. (9), Para. 4.4.1.3 lateral seismic loads on 1990, and 1991.
Ref. (34), vertical-only SSS small Question D.3.a bore pipe supports. Modify the supports if necessary.
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'5 SEP (1) , Item-Status (3)
,L__Ippic .. ; Reference' Documents (2). , . Commitment' Si--rv Hgghnr.
III-6 Ref.~(9),' Para. 4.4.2 ' Modify gang: supports for . Scheduled for 1988 47 Ref. (34).. Question D.39 SSS piping to sustain NRC and 1991.
. spectrum seismic loads l using one of three methodologies found acceptable to the NRC.
III-6' Ref.-(9), Para. 4.4.1.1 ' Revise Calculation YRC-388 COMPLETED: Eccentric 48 Ref. (34), to account for the , mass does not affect
- - Question D.30.1 eccentric mass of valve the calculation.
Ref.-(79) VD-TV-401A.
III-61 Ref. (9), Para. 4.4'2. Provide a basis for the COMELEIED: This- 49' Ref. (34), Question E.23 - ' use of U-bolts as axial request is withdrawn.
restraints using one of U-bolts-will not be four methodologies found used.as axial acceptable to the NRC. restraints. No further action required.
zIII-6 Ref. (3), Item 13 Include in the ISI Program EDMELEIED: Since 50 Ref. (9), Para. 5.2 all U-bolts which are used U-bolts will not for axial restraint of SSS be used for axial piping. restraint, none will be added to the ISI Program.
III-6 Ref. (3), Item 18 Verify that concrete Scheduled for 1988, 151 Ref. (9), Para. 4.4.1.3 expansion anchors in SSS 1990, and 1991.
Ref. (34), Question D.15 pipe supports have an Note that DC-1 acceptable factor of requires a F.S.
safety. of 4 or 5.
III-6 Ref. (3), Item 14 Address the concerns of IE EDMELEIED: All 52 Ref. (9), Para. 4.4.1.3 Notice 86-94 regarding the existing 1/2-inch Ref. (34), Question D.40 use of 1/2-inch Hilti . Hilti bolts were found Ref. (60) bolts. to be acceptable. New bolts will meet the new design criteria.
III-6 Ref. (3), Item 3 Modify the feed and bleed Scheduled for 1990. 53 Ref. (9), Para. 4.5.2 heat exchanger supports end Ref. (34), surrounding block walls to Question F.8.b sustain NRC spectrum Ref. (38) seismic loads.
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SEP (1) , .
Item' Topic ' Reference Documents (2) Commitment Sr-- rv Status (3) Number III-6 Ref. (1),. Para. 4'.11.2 Modify.the supports for Scheduled for.1991. 54-Ref. (3), Item 7 all large and small bore Ref. (9), Para. 4.4 SSS piping outside' .
containment to sustain NRC-spectrum seismic loads.
- III-6 Ref. (3), Item 4 Modify the bracing.for the CDMELETED: 55 Ref. (9), Para. 4.5.1 component. cooling surge PDCR 87-017.
Ref. (34), -tank to sustain NRC Question G.9.111 spectrum seismic loads.
III-6 Ref. (1), Para. 4.11.3 Provide seismic anchorage To be resolved. 56 and 4.11.4 for RPS/CIS/NRV conduit / through USI A-46 Ref. (3), Item 10 . cable. trays and other SSS- SQUG walkdown.
Ref. (9), Para. 4.6 ' electrical / mechanical Schedule to be Ref. (34), Question G.1 equipment in conformance- determined.
Ref. (55) with Generic Letter 87-02.
-III-6 Ref. 55 Qualify and/or modify SSS To be included in 57 '
Ref. 72 equipment within the NRV SQUG walkdown.
Ref. 73 enclosure to sustain NRC Schedule to be' spectrum seismic loads. determined.
III-7.B Ref. (2), Para. 2.6 Evaluate the weld and shell COMPLETED: No' 58 Ref. (11) stresses in the VC column- further action Ref. (57) to-shell connection under required.
Ref. (58) combined NRC seismic and Ref. (59) LOCA loads.
Ref. (74)
III-7.D Ref. (18) Perform structural RESQLEED: This 59 Ref. (19) integrity testing of the testing is VC in conformance with the performed on a requirements of SRI-3.8.2. scheduled basis.
III-10.A Ref. (1), Para. 4.14.1 Perform a one-time COMPLETED: These 60 Ref. (2), Para. 4.4 demonstration test (trip tests have been
- Ref. (6) set point) of thermal performed.
L *Ref. (8) overload protection for Ref. (20) MOVs powered by the Engineered Safety Features (ESF) buses.
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1SEP;(1)L, .
Item.
Status (3)-
Topic Reference' Docuiuenta' (2) Commitman.t Se rv Bucher V-10.B. Ref.L(1), Para. 4.19.4 Develop' procedures.for COMPLETED: 61
.Ref. (2) post-incident cooling. EDCR 81-3'.' : Plant- -
Procedurer 0P-2156, OP-2162, and'0P-2705.
V-10.B' *Ref. (6) . Modify the auxiliary .CDMPLETED:. 62.
Ref. (21) .
feedwater system and. EDCRs 79-16 and.
-Ref.-(22)- install a Post-Incident 81-02..
Ref..(75)1 . Cooling System.to meet
=V-11.B. the functional requirements VII-3 ~o f BTP RSB 5-1 (GDC 4).
~
h .V-10.B ~ Ref. (1),.. Para. 4 19.5
. Install an interlock on COMELEIED: 63-
- Ref. (2), Para. 4.5.1- one valve on both the EDCR 83-25.
- Ref.-(6)- inlet and outlet of'the
.Ref. (22). Shutdown Cooling System.
V-11.B VII-3 e !VI-1 Ref. (1), Para. 4.21.1 Inotall trisodium COMPLETED:' 64 Ref. (2).. Para. 2.7 phosphate containers- EDCR.84-320.
Ref. (23) .inside the VC to control Ref. (24)- post-accident water chemistry.
VI Ref. (1), Para. 4.21.2 Develop and i.mplement an- RESOLVED: 65-
- Ref. (8) inspection program to These inspections evaluate the condition of are now being .
the painted surfaces of' performed using the VC. OP-5927.
'VI-4; Ref. (1), Para. 4.22.6 Remove the low pressure COMELEIED: 66-p *Ref. (6) surge tank from the EDCR 83-10;
[: Ref. (25) containment isolation. Proposed Change Ref. (26) Affected Penetrations: No. 180, 3, 4, 10, 37, 40, 41, Amendment No. 86.
87, 88, 94 and 96.
VI-4. Ref. (26) Cut and cap the COMPLETED: 67 l purification tie-in to EDCR 83-10.
I~ the Low Pressure Safety Injection System removing PU-V-649 as an isolation valve. Affected Penetration: 3.
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'a SEP (1) , Item Topic Reference Documents (2) Commitment Summary Status (3) knbar
~VI-4 Ref. (1), Para. 4.22.7 Develop a post-accident RESOLVED: Proposed 68 and 4.22.8 procedure to require the Change No. 180, j
- Ref. (25) steam generators to be Amendment No. 86.
Ref. (26) Illied above the level of the tubes and pressurized to greater than the -
absolute pressure of the i containment. Affected l Penetrations: 79 through 86. )
i VI-4 Ref. (1), Para. 4.22.11 Ensure that all test, vent, COMELEIED. 69 Ref. (25) and drain lines penetrating Ref. (26) containment have at least Ref. (80) one seal-closed valve.
VI-4 *Ref. (25) Relocate the air COMELEIED: Proposed 70 Ref. (26) particulate monitor to Change No. 198, a location inside Amendment No. 96 containment. Affected Penetrations: 64 and 65.
VI-4 Ref. (1), Para. 4.22.1.2 Add a blank flange inboard COMPLEIED: Proposed 71 Ref. (25) of the manual valve on the Change No. 198, Ref. (76) fuel chute dewatering pump Amendment No. 96.
- Ref. (77) discharge line. Affected Penetration: 78.
VI-7.A.3 Ref. (1), Para. 4.23 Test automatic valves in RESOLVED: Proposed 72
- Ref. (5) the Emergency Core Cooling Change No. 139, Ref. (27) Actuation System. Supplement No. 5 Amendment No. 83.
VI-10.A Ref. (1), Para. 4.24 Include the present REEOLVED: Proposed 73
- Ref. (5) response-time testing Change No. 139, Ref. (27) program for all Reactor Supplement No. 5, Protection Systems in the Amendment No. 83.
Technical Specifications.
VII-1.A Ref. (1), Para. 4.25 Remove the selector switch COMELEIED: 74 Ref. (28) which allows the wide- EDCR 84-307.
range pressurizer level channel to drive the narrow-range channel.
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- SEP (1) , Item Topic Reference Documents (2) Ccmmitment So--ary Status (3) Number LVIII-1.A1 Ref.-(1), Para. 4.27 Develop procedures for .REEQLVED
- 75
- Ref.;(6) diesel generator load . Plant Procedures Ref.'(29) sheddings. OP-3838, OP-3844, and OP-3845 have been revised.
.VIII-1.A *Ref. (6) Install degraded grid COMPLETED: 76 Ref. (29) modifications and make. EDCR 80-48, Proposed the associated Technical Change No. 183, Specification changes. Amendment No. 84.
VIII-3.B. Ref.-(1), Para. 4.28.1 Check plant batteries for BESOLVED: Test and 77 Ref.'(2), Para. 2.9.1 loose connections and and surveillance
- Ref. (30) corrosion buildup.. procedures are being followed.
'IX . Ref. (1), Para. 4.31.3 Modify the DGB Ventilation CQMPLETED: 78
- Ref. (6) System to eliminate the EDCR 83-33.
potential for a single active failure.
IX-5 Ref. (1), Para. 4.31.4 Modify plant procedures REEDLVED: NRC .79 regarding the Battery Room recommendations Ventilation System. were incorporated in Rev. 4 of both Procedures OP-3708 and OP-3709.
XV-i* Ref. (1), Para. 4.35 Impose a Technical RESOLVED: Proposed 80
- Ref. (5) Specification limit on Change Nos. 139/185,
- Ref. (8) long-term leakage from Amendment No. 90.
Ref. (14) ESF components outside containment.
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REFERKNCES (1)- Integrated Plant Safety Assessment (SEP), NUREG-0825, June 1983.
(2) Integrated Plant Safety Assessment (SEP), NUREG-0825, Supplement No. 1, October 1987.
(3) Le'ter t from YAEC to NRC (FYR 87-056), "SEP Topic III-6 Commitment Summary,"' dated June 1, 1987.
(4) Letter from NRC to YAEC (NYR 84-10), " Inspection Report 83-15," dated January 10, 1984.
(5) Letter from NRC'to YAEC (NYR 84-93), " Inspection Report 84-01," dated May 8, 1984.
(6) Letter.from NRC to YAEC (NYR 85-31), " Inspection Report 84-20," dated February 4, 1985.
(7) Letter from NRC to YAEC (NYR 85-72), " Inspection Report 85-04," dated April 12, 1985.
(8) Letter from NRC to YAEC (NYR 85-111), " Inspection Report 85-11," dated
. July 8, 1985.
(9) Letter from NRC to YAEC (NYR 87-142), "NUREG-0825, Section 4.11, Seismic Design Considerations," dated July 16, 1987.
(10) Letter f rom NRC to YAEC (NYR 87-86), 'WUREG-0825, Section. 4.5, Wind and Tornado Loading and Section 4.8, Tornado Missiles," dated May 13, 1987.
(11) Letter from NRC to YAEC (NYR 87-141), "NUREG-0825, Section 4.12, Design Codes, Design Criteria, and Load Combinations, TAC No. 63464," dated July 16, 1987.
(12) Letter from NRC to YAEC (NYR 87-140), "IPSAR Section 4.9, Effects of Pipe Breaks on Structures, Systems, and Components Inside Containment,"
dated July 16, 1987.
(13) Letter from YAEC to NRC (FYR 86-084), " Response to Requests for Additional Information, SEP Topics III-2 and III-4.A," dated September 5, 1986.
(14) Letter from YAEC to NRC (FYR 82-120), " Yankee Integrated Assessment Performed for SEP," dated December 23, 1982.
(15) Letter from NRC to YAEC, "SEP Topic II-2.0 Atmospheric Transport and Diffusion Characteristics for Accident Analysis," dated September 4, 1981.
i (16) Letter from YAEC to NRC (FYR 81-95), "SEP Topic Assessments," dated June 30,1981.
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(17) . Letter from YAEC to NRC (FYR 87-57), "SEP Topic III-7.B," dated June 2,1987.
(18) Letter from NRC to YAEC (NYR 82-68), " Containment Structural Integrity Testing," dated March 18, 1982.
(19) Letter from YAEC to NRC (FYR 81-152), "SEP Topic Assessment Completion,"
dated November 18, 1981.
(20) Letter from YAEC to NRC (FYR 84-37), "SEP Topic III-10.A," dated March 22, 1984.
(21) Letter from NRC to YAEC, "SEP Topic V-11.A Requirements for Isolation of High and Low Pressure Systems; and V-11.B. RHR Interlock Requirements Final Safety Evaluation Report," dated July 27, 1982.
(22) Letter from NRC to YAEC (NYR 82-15), "SEP Topics V-10.B. RHR System Reliability; V-11.B, RHR Interlock Requirements; and VII-3, Systems Required for Safe Shutdown," dated February 1, 1982.
(23) Letter from YAEC to NRC (FYR 84-100), "SEP Topic VI-1," dated September 28, 1984. .
(24) Letter from NRC to YAEC (NYR 84-227), "IPSAR Section 4.21.1, Sump Water
~
Chemistry," dated November 19, 1984.
(25) Letter from NRC to YAEC (NYR 86-197), "NUREG-0825, Section 4.22, Containment Isolation," dated August 28, 1986.
(26) Letter from YAEC to NRC (FYR 83-34), "SEP Topic VI-4, Containment Isolation," dated March 16, 1983.
(27) Letter from NRC to YAEC (NYR 82-120), "SEP Topics VI-7.A.3 and VI-10.A."
dated June 10, 1982.
(28) Letter from NRC to YAEC (NYR 82-43), "SEP Topic VII-1.A, Isolation of RPS from Nonsafety Systems, Including Qualification of Isolation Devices, Safety Evaluation," dated February 22, 1982.
(29) Letter from YAEC to NRC (FYR 84-39), "SEP Topic VIII-1.A, Degraded Grid," dated March 28, 1984.
(30) Letter from NRC to YAEC (NYR 85-159), "IPSAR Section 4.28.1 Battery Current Charge / Discharge and Fuse Open Alarm," dated September 19, 1985.
(31) Letter from YAEC to NRC (FYR 86-120), " Response to Requests for Additional Information, SEP Topics III-2 and III-4.A," dated December 17, 1986.
(32) Letter from YAEC to NRC (FYR 85-01), "SEP Topics III-2 and III-4.A,"
dated December 31, 1984.
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(33) ' Letter from NRC to YAEC (NYR 87-18), "YNPS - Analysis of the Main Steam
'and Feedwater Piping and Support Structure," dated February 2, 1987.-
(34) Letter from YAEC to NRC (FYR 87-24), "SEP Topic III-6. Technical.
Information," dated March 9, 1987, Attachment 1, Item B.7.
'(35))-Letter from YAEC to NRC (FYR 84-01), "SEP Topic II-3.0," dated December 30, 1983.
- . (36) Letter from YAEC to NRC (FYR 84-90), "SEP Topic II-3.0," dated August 28,;1984.
(37) l Letter from NRC to YAEC (NYR 82-228), "SEP Topic II-4.F Settlement of Structures and Buried Equipment,". dated September 16,.1982..
(38) Letter from YAEC to NRC (FYR 87-102), " Response.to Inspection 87-01 Masonry Walls," dated-September 25, 1987.
(39) Letter.from NRC to.YAEC (NYR 82-203), "SEP Topic III-2, Wind and Tornado Loadings," dated August 31, 1982.
(40) Letter from YAEC to NRC (FYR 86-116), "SEP Topic III-7.B," dated December 4, 1986.
(41):' Letter'from YAEC to NRC (FYR 87-58) "SEP Topic III-7.B," dated June 4, 1987.
(42) Memo from Carter to Haseltine, (YRP 778/87), " Summary of Reactor Vessel Sliding Inspection Program," dated August 6, 1987.
(43) Letter from NRC to YAEC (NYR 82-234), "SEP Topic III-3.C. In-Service
-Inspection of Water Control Structures," dated October 4, 1982.
(44) Letter from YAEC to NRC (FYR 84-36), "SEP Topic III-5.A " dated March 23, 1984.
(45) Letter from NRC to YAEC (NYR 84-91) ,'.'IPSAR Section 4.9, Effects of Pipe Breaks on Structures, Components, and Systems Inside Containment," dated May 3, 1984.
(46) Letter from YAEC to NRC (FYR 87-027), "SEP Topic III-5.A," dated April 10, 1987.
(47) Letter from YAEC to NRC (FYR 87-054), "SEP Topic III-5.A," dated May 27, 1987.
(48) Letter from YAEC to NRC (FYR 85-32), "SEP Topic III-5.A," dated l March 15, 1985.
(49) Letter from YAEC to NRC (FYR 84-99), " Resolution of SEP Topic III-5.A, Item 1," dated September 27, 1984.
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(50) , Letter from YAEC to NRC (FYR 86-092), "SEP Topic III-5.A." dated' October 1, 1986.
(51) Letter from NRC to YAEC (NYR 82-142), "SEP Topic III-5.B. Pipe Break Outside Containment," dated June 29, 1982.
(52) Letter from YAEC to NRC (FYR 87-67), "SEP Topic III-6, Reactor Pressure Vessel," dated June 30, 1987.
(53) Letter from YAEC to NRC (FYR 88-01), "SEP Topic III-6, Reactor Pressure Vessel / Neutron Shield Tank Seismic Response and ARS Generation," dated January 4, 1988.
(54) Letter from NRC to YAEC (NYR 87-25), "YNPS - Example Piping Analyses,"
dated February 2, 1987.
(55) Letter from NRC to YAEC (NYR 87-045), " Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors, USI A-46 (Generic Letter 87-02)," dated February 19, 1987.
(56) Letter from YAEC to NRC (FYR 87-085), "SEP Topic III-7.B Snow Loads,"
dated September 8, 1986.
(57) Letter from YAEC to NRC (FYR 87-112), "SEP Topic III-7.B. Design Codes, Design Criteria, and Load Combinations," dated October 28, 1987.
(58) Letter from NRC to YAEC (NYR 87-202), "SEP Topic III-7.B," dated November 6, 1987.
(59) Letter from YAEC to NRC (FYR 87-99), "SEP Topic III-7.B," dated September 18, 1987.
(60) Memo from LeFrancois to Haseltine (YRP 797/87), " Evaluation of Information Notice 86-94: Hilti Concrete Expansion Anchor Bolts," dated August 7, 1987.
(61) Memo from Holmgren to Haseltine (YRP 588/87), "SEP Topics III-2 and III-4. A, Safety Evaluation," dated June 19, 1987.
(62) Memo from Follen to Holmgren (SA 87-110), " Tornado - Wind Cost-Benefit Analysis," dated September 16, 1987.
(63) Memo from Holmgren to Haseltine (YRP 954/87), "SEP Topic III-6, Safety Evaluation, " dated September 28, 1987.
(64) Memo from Holmgren to Haseltine (YRP 920/87), "SEP Topic III-7.B. Safety Evaluation," dated September 16, 1987.
(65) Memo from Carter to Haseltine (YRP 784/87), "SEP Topic III-5.A, Safety Evaluation," dated August 14, 1987.
(66) Memo from Holmgren to Haseltine (YRP 1043/87), "In-Service Inspection of Water Control Structures," dated October 23, 1987.
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(67) , Memo from Labrecque to Holmgren (YRP 673/87), " Review of SEP Topical SERs for Plant Commitments," dated July 10, 1987.
(68) Letter from YAEC to NRC (WYR 80-49), " Seismic Evaluation," dated May 7, 1980.
(69) ' Letter from NRC to YAEC (NYR 83-21), "SEP Topic III-6, Seismic. Design Considerations," dated February 1, 1983.
(70) Memo from LeFrancois to Holmgren (YRP 169/88), " Review of Small Bore Isometric Drawings," dated February 16, 1988.
(71) Letter from NRC to YAEC (NYR 86-45), " Snow Loads," dated March 10, 1986.
(72) Memo from Lucas to Distribution (YRP 772/84), " Seismic Equipment Upgrade List," dated August 23, 1984.
(73) EDCR 85-301, " Appendix R - Emergency Lights," Change No. 1, dated December 19, 1985.
(74) Memo from Hol',gren:to Haseltine (YRP 336/88), "SEP Topic III-7.B," dated March 24, 1908.
(75) Letter from YAEC to NRC (FYR 81-157), " System Description Post-Incident Cooling System," dated November 30, 1981.
(76) Letter from YAEC to NRC (FYk 86-004), " Replacement of a Manual Containment Isolation Valve With a Blank Flange in Table 3.6.1 of the Technical Specifications," dated January 8, 1986.
(77) Letter from NRC to YAEC (NYR 86-128), " Changes to Technical Specifications," dated June 9, 1986.
(78) Memo from LeFrancois to Holmgren (YRP 352/88), " Generation of ARS for Analysis of SSS Piping in the Vapor Container," dated March 28, 1988.
(79) Memo from Fucito to Holmgren (YRP-507/88), "SSS Piping Calculation YRC-388," dated April 25, 1988.
(80) Memo from Desilets to Williams (RE 88-24), " Test, Vent, and Drain Line Containment Isolation Boundaries," dated September 20, 1988.
(81) Memo from Philley to Holmgren (YRP 2048/88), " Investigation of Masonry Wall Strap Anchors," dated October 7, 1988.
E00lHQIES (1) Refer to NUREG-0825 for SEP Topic Descriptions.
(2) References noted with an asterisk (*) document NRC audits, inspections, reviews, or other closure verification.
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. zo..., As.
. ;, u .,
(3K ,CG1Fl&TED.conunitments are th6se which ' require a plant modification' or y' evaluation which has!now been made. Commitisents.which'have been RESOLVED are.those which require ongoing activity such as-periodic,
-inspection;or adherence.to a Technical Specification. .All other
. commitments are presently incomplete.
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