ML20207R902
| ML20207R902 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 03/11/1987 |
| From: | Withers B WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20207R903 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-01.120, RTR-REGGD-1.097, RTR-REGGD-1.120 WM-87-0063, WM-87-63, NUDOCS 8703180281 | |
| Download: ML20207R902 (27) | |
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o' CREEK NUCLEAR OPERATING CORPORATION March 11, l')97 Document Control Desk U. S. Nuclear Regulatory Comission Washington, D. C. 20555 Letter: WM 87-0063 Re: Qocket No. 50-482 Subj: Pavision O of the Wolf Crmk Updated Safety Analysis Report Gentlemen:
The purpose of this letter is to document the sutriittal of the Wolf Creek f} Updated Safety Analysis Report (USAR), Pavision 0, and to provide a Q description of the changes made since issuance of Facility Operating License No. NPF-42.
As required by 10 CFR 50.4, 10 CFR 50.34, 10 CFR 50.54 (a) (3), and 10 CFR 50.71 (e) eleven copies of the Wolf Creek Updated Sa fety Analysis Report have been shipped to the Document Control Desk. These copies were shipped via United Parcel Service on March 11, 1987.
Specific technical changes which have been made since issuance of the operating license are described in the attachment to this letter. In addition to thefe technical changes, Wolf Creek Nuclear Operating Corporation has de the following administrative enhancements:
- 1) The Wglf Creek USAR combines the SNUPPS Final Safety Analysis Report and Wolf Creek Site Addendum into a single document.
- 2) Organization descriptions from chapters 13, 17 and the Fire Protection Plan have been consolidated into section 13.1 to eliminate redundancy.
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8703180281 870311 PDR ADOCK 05000482 PO Box 411 Burtington KS 66839 Phone (3161364 8831 An Ecuai Ocoorvty E power M F M VET l K PDR L
, WM 87-0063 - -
Page 2 i
- 3) The Wolf Creek Radiological Dnergency Response Plan has been removed from the USAR and is maintained and submitted as a separate controlled document. This allows the Plan to be updated on a more frequent basis without creating confusion with USAR revisions.
If you have any questions concerning this matter, please contact me or Mr.
O. L. Maynard of my staff.
Very truly yours, 1 1
v '-f _
Bart D. Withers President and Chief Executive Officer BDW:jad Attachment l
cc: PO'Connor (2)
RMartin JCumnins l
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1 STATE OF KANSAS )
) SS CITY OF BURLINGr!ON )
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l Bart D. Withers, of lawful age, being first duly sworn upon oath says that he is President and Chief Executive Officer of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the content thereof; that he has executed that same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
By ed Bart D. Withers President and Chief Executive Officer s
SUBSCRIBED and sworn to before me this // day of'818(eJ , 1987.
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~4 - "- ' Expiration Date 8 - 4' /990
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Attachment to WM 87-0063 March 11, 1987
- page 1 USAR CHANGE REQUESTS Wolf Creek Affected Change Request Portion Description of Change 85-001 pg. 2.2-28 Section 6.4 of the USAR states the chlorine monitors must be capable of providing an alarm within 7 seconds. Section 2.2 has been revised to be consistent with USAR Section 6.4 and the Purchase Specification.85-003 pg. 9.5-13 These changes on the Control pg. 9.5-28 Rocan Halon System were sent tab. 9.5.1-2(sh. 3) to the NRC in IC4LNRC 85-028 tab. 9.5A-1 (sh. 50) prior to receipt of the Wolf Creek License.85-005 tab. 3. ll(B)-3 (sh. 128) We conveyor system controls for the fuel transfer system are non-Q, non-IE.85-006 pg. 4.4-45 These changes were sent to the pg. 5.4-47, 48 NRC via SLNRC 85-001 prior to pg. 7.2-36 receipt of the Wolf Creek pg. 9.1-45, 46 License. Section 9.1 was pg. 14.2-169 modified slightly to clarify pg. 14.2-176 the tygon hose connection.85-007 tab. 3.2 These changes were sent to the tab. 3.2-1 1 NRC in SLNRC 85-003 prior to ques. 430.1 receipt of the license. The text has been modified to be more appropriate to USAR format.85-009 pg. 6.4-1, 4, 7 This change clarifies the pg. 9.4-12, 13, 17 location of carbon dioxide /
carbon monoxide monitors.
- 1. The Wolf Creek Generating Station Semiannual Radioactive Effluent Release Report covering the period from July 1, 1986, through December 31,1986 (WM 87-0056, dated 3/2/87), stated that any major changes to Radwaste Treatment Systems would be provided in the next annual update of the Final Safety Analysis Report. Were have been no licensee-initiated major changes to the Radwaste Treatment Systems since Wolf Creek Generating Station was initially licensed. Any future major changes made to the Radwaste Treatment Systens will be described in Semiannual Radioactive Effluent Release Reports as allowed by Technical Specification 6.15.
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. 1 Attachment to WM 87-0063 March 11, 1987 page 2 i
USAR CHANGE REQUESTS Wolf Creek Affected Change Request Portion Description of Change 85-011 pg. 5.4-7 This change clarifies the turbine generator pump overspeed test.
- 85-012 pg. 15.6-25, 31, 38 These changes clarify the Section 15.6 text. Reference 2 was updated 1
( to reflect the latest informtion. I 85-013 pg. 18.2-37 mese changes clarify the basis for the pressurizer heater capacities and correct minor inconsistencies within the USAR.
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85-014 tab. 9.2-3 (sh. 2) 2ere are three air conpressors and after coolers with one in use.85-015 pg. 8.1-6 RG 1.9 allows engineering analysis !
- to be used to justify a greater
! percentage than 60 percent of each load sequence interval. This change reflects the fact that WCNOC may utilize this option.85-016 tab. 9.4-2(sh. 15) Revision 17 of the SNUPPS FSAR tab. 9.4-3 (sh. 10) revised these two tables to reflect the fact that the second bank of HEPA filters was inaccessible.
Wese two corrections were omitted at that time.85-018 fig. 6. 2. 4-1(sh. 35, This change corrects several errors 69b) in the penetration list by adding two valve penetrations and correcting a typographical error.85-020 pg. 7.3-28 This change corrects the I
description of the main feedwater/
main steam isolation valve fast l closing capabilities. mis change was sent to the NRC prior to
, receipt of the license in KMLNRC 85-060.
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Attachment to WM 87-0063 March 11, 1907
. pagm 3 UhARCHANGEREQUESTS Wolf Creek Affected Change Request Portion Description of Chance 85-021 pg. 18.2-30 This change updates information on pg. 18.3-13 primary PORV and safety valve pg. 3.ll(B)-18 testing, adds reference to identify the Wolf Creek program to reduce leakage from systems outside containment that contain radioactive fluids, and updates the discussion on control systems interactions.85-022 pg. 13.2-14 The requirements of the accelerated requalification program are revised to be in accordance with ANSI 3.1-1978.85-023 pg. 5.4-14 % e material description of the steam generator J tubes has been changed to show they are fabricated from Inconel-600.
1 85-025 pg. 4.4-43 This change corrects the description of the reactor coolant i
i flow test performed prior to initial criticality to make it consistent with USAR section 14.2.12.3.5.85-026 pg. 11.3-11 mis change modifies the value of the hydrogen reccinbiner high discharge hydrogen concentration alarm.
i 85-027 fig. 8.3-2 This change adds the ESW chlorination building unit heaters to the list of loads supplied by the emergency diesel generator.85-029 pg. 15.1-25 This change incorporates updates pg. 15.2-13, 18, 26 to chapter 15 resulting from a July pg. 15.3-16 1984 audit of the WCGS pg. 15.4-50 Safety Analysis performed by pg. 15.5-7 SNUPPS.
pg. 15.6-31 tab. 15.2-1 tab. 15.5-1 fig.15.2-9 thru 14 fig. 15.5-4 thru 11
Attachment to WM 87-0063 March 11, 1987
. page 4 USAR CHANGE REQUESTS Wolf Creek Affected Change Request Portion Description of Change 85-030 pg. 4.2-15, 39, 41, 43 This change revises the control rod pg. 4.3-4 guide tube description, updates the tab. 4.3-2 quality control inspection description, and corrects two typographical errors.85-031 pg. 3A-13 Wis change provides further pg. 3A-47 information regarding compliance with Regulatory Guides 1.30 and 1.116. It was sent to the NRC in EMLNRC 86-041 and 85-095.85-034 tab. 13.1-1 This change makes the minimum qualifications for plant personnel consistent with industry standards and regulatory guidance.85-035 fig. 9.3-1 Mis reflects modifications to the compressed air system to improve operability and maintenance.85-036 tab. 3.2-4 mis corrects the issue date of revision 3 to Regulatory Guide 1.26.85-037 pg. 8.3-30 This change clarifies the WCGS tab. 9.5A-1(sh. 28) compliance with electrical raceway pg. 9.5B-5 & 6 and cable separation requirements.
This change was sent to the NRC prior to receipt of the license in lHLNRC 85-030 as modified by 85-140.85-039 pg. 7.2-2, 3, 16, 28, This adds a description of the 29, 30, 32 automatic shunt trip modification to the reactor trip breakers.85-041 pg. 9.5-9, 26 This change describes a design modification to the fire protection system to prevent accidental de-energization and deluge of the ,
startup or any of the three main I transformers.
Attachment to WM 87-0063 tiarch 11, 1987
. paga 5 USAR CHANGE REQUESTS Wolf Creek Affected Change Request Port. ion - Description of Change 85-042 pg. 9.5-42 A six inch sample line has been fig. 3.8-112 added to the emergency fuel oil q storage tanks.85-043 pg. 14.2-174 This change identifies the fact pg. 3A-26 that the results of the RCCA or ques. 640.6 Bank Worth Measurement at power start up test (S-07SF09) performed at Callaway were applied to Wolf Creek and the test was not performed at WCGS. Bis exemption was requested by KMLNRC 85-119 and was approved in a July 3, 1985 letter froni the NRC.85-045 pg. 5.2-35 This change reflects the effect of charging system configuration modifications resulting from isolation of the boron injection surge tank on the systems ability to withstand and detect RCS isolation valve leakage.85-046 pg. - 3A-22 Wis change updates the edition of Stfr-TC-1A which the Operating Agent uses to certify NDE personnel.85-049 pg. 15.0-7 This change incorporates tab. 15.0-2, 3 modifications to chapters 6 and 15 ,
tab. 15.1-5, 12, 19 resulting from a July 1984 audit I fig. 15.1-7 of the WCGS safety analysis pg. 15.2-12, 13, 18 performed by SNUPPS. l pg. 15.3-10 '
pg. 15.4-4, 5, 17, 40, 43 tab. 15.4-3 fig. 15.2-10 pg. 6.2-28, 30, 31, 34, 36, 96, 97 tab. 6.2.1-56 Fig. 15.4-2 l
85-051 tab. 3.9(B)-16 Wis change updates the USAR table (sh. 1, 3, 8, on active valves to make it 9, 11, 15, 23, consistent with other design 24, 25, 26, documents.
and 27)
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Attachment to WM 87-0063 March 11, 1987 i
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USAR CHANGS REQUESTS l l
Wolf Creek Affected Change Request Portion Description of Change 85-053 tab. 3.2-1 This change: (1) updates the USAR tab. 3.2-2 (sh 1) list of safety related equipnent pg. 3. 7 (B)-2, 4, to make it consistent with other 11, 19 design documents (2) removes pg. 3.7 (B) A-6 unnecessary figures that are not pg. 3.9(B)-1, 3, referenced in the text (3) corrects 4, 10 .
several figure and section 1
tab. 3.9(B)-1, 14 references and (4) makes minor editorial or typographical changes.
pg. 3.10(B)-3, 4 pg. 3. ll(B)-4, 13 tab. 3.9 (B) A-1 l fig. 3.7(B)-llA, B l fig. 3.7(B)-16 l ques. 270.1 i 85-054 pg. 3.6-5, 6, 9, 11, Wis incorporates many small
, 13, 20, 22 editorial and consistency-related j pg. 38-1, 2, 5, 10 changes to the pages identified. '
11, 12 pg. 3A-8, 15, 30, 32, 40, 45 1
85-053 tab. 9.1-7 Wis change corrects the maximum l load and normal expected load range ;
values for the spent fuel pool I bridge crane.85-056 pg. 9.3-3 This change notes that both parallel trains of the instrument air dryer / filters can be used simultaneously.85-057 pg. 15.2-13 This change: (1) corrects the fire pg. 9.5B-213, 214, rating of the south wall of the l 215 rad waste tunnel, and several walls '
! pg. 9.4-1, 3, 4, in turbine building fire area T-2 5, 7, 11, 12, 14 (2) adds information on the air tab. 9.4-4 handling vent serving the l pg. 9.5B-221, 222, Secondary Alarm Station room, 2 (3) adds information on reports tab.33 11.3-1 doctnenting RVLIS performance, and ques. 492.32 (4) makes several minor changes of I.
fig. 9.5.1-2 (sh. 1) an editorial nature.
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Attachment to WM 87-0063 March 11, 1987 l page 7 )
USAR CHANGE REQUESTS Wolf Creek Affected Change Request Portion Description of Chance 85-058 pg. 8.2-3, 4, 5, 7 This change reflects the addition fig. 8.2-3 of the number 7 transformer in the Wo lf Creek substation to provide i another source of offsite power to I feed Class IE loads, l
85-059 fig. 10.4-2(sh 6) The changes to these figures show fig. 9.3-5(sh 7) the design modifications undertaken fig.10.4-6 (sh 7, 8) to prevent steam introduction into ,
fig. 10.4-10 the condenser air removal system. ;85-060 pg. 12.1-10 This change makes the operating Agent's Quality Division responsible for review and audit of the radiation protection program.
1 85-061 tab. 1.3-1 This change corrects several figure pg. 6.4-4, 5, 6, 7 and section cross references and i pg. 6.5-5, 8, 10, 13 nakes other minor changes to pg. 6.6-2 establish consistency between USAR pg. 7.1-9 sections.
pg. 7.3-4, 25, 41 pg. 3.8-30, 46, 54 pg. 5.2-29 pg. 7.4-1, 2 pg. 8.1-16 85-062 pg. 6.2-10, 47, 56, This change incorporates many 59, 70, 71 small editorial and consistency-tab. 6.2.4-2 related changes to the pages pg. 15.1-25 identified.
tab. 15.1-4 tab. 15.6-3 tab. 1.6-1, 2 pg. 2.2-13 pg. 2.3-56 tab. 2.3-59d, 78, 79 tab. 2.4-41 tab. 3.4-1 pg. 2.5-1 85-063 pg. 6.2-53 This change corrects the design tab. 6.2.2-2 (sh. 2) code of the containment spray system spray nozzles and clarifies the shop testing performed on the spray pumps.
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Attachment to WM 87-0063 March 11, 1997 page 8 USAR CHANGE REQUESTS Wo lf Creek Affected l Change Request Portion Description of Change
,85-064 tab. 12.3-2 This change moved the portable I radiation monitor to the '
manipulator bridge crane and revised the high alarm.
l 85-066 pg. 8.2-1 This change incorporates several
- pg. 9.1-13, 28 small editorial changes to the pages identified.
tab. 9.1-4 (sh 4) pg. 9.2-25, 32, 37 46, 50 tab. 9.2-16 i
85-067 tab. 7.2-13 This corrects the typical response time for overtenperature and overpower delta T trip signals.
!85-068 pg. 9.1-52 This change deletes a statement that would have required road dirt to be hosed off spent fuel shipping casks prior to entry into the fust building. The change was made due to radiological concerns.85-069 pg. 12.3-5 This change clarifies the fact that only pipe runs which are radioactive are of an ALARA Concern.
- 85-070 tab. 6.2.2-7 This change reflects the "as ,
l fig. 6.2.2-5 supplied" performance character-l tab. 6.3-1 istics of the containment spray and residual heat removal pumps. i l
l 85-071 pg. 9.5-19 This change corrects references for test method and acceptance criteria related to fire dampers and doors.
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Attachment to WM 87-0063 March 11, 1907
. paga 9 USAR CHANGE REQUESTS Wolf Creek Affected Change Request Portion Description of Change 85-072 pg. 3.1-2, 4, 9, 11, This change: (1) reflects changes l 23, 28, 30, 31, 33, to plant configuration resulting '
34, 35, 37, 43 from the lower requirements on i pg. 5.2-33, 37, 38, 43 boron injection tank boron pg. 5.4A-2 concentration (2) clarifies that l tab. 5.4A-3 either manual or automatic controls (sh. 1, 3, 13) can terminate dilution and initiate tab. 7A-2 boration (3) incorporates many pg. 7A-4 editorial changes to the pages identified. !85-073 pg. 3.10(B)-1 his change expands exceptions to pg. 3.8-55 AWS D1-1 and adds cross references for the appropriate exceptions.85-074 pg. 11.5-4 This identifies that surveillances on radioactivity monitors are done in accordance with Technical Specifications.85-075 Section 1.7 This updates all design drawings to Cesign Drawings as-built configurations.85-076 pg. 12.3-39 This change revises the safety evaluation section of the airborne radioactivity process monitors to: 1 (1) delete reference to a methodology for detecting low concentrations of halogens and l noble gases (2) delete reference to a laboratory analysis of ratios l among the various species of airborne radioactivity (3) modify the description of the AiRMS.85-080 pg. 12.3-1, 2 mis change explains the capability l to monitor radiation levels inside {
filter and domineralizer resin l compartments.
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O Attachnent to '4187-0063 March 11, 1987
. page 10 USAR CHANGE REQUESTS Wolf Creek Affected Change Request Portion Description of Change 85-082 pg. 8.3-1 mis change: (1) revises the tab. 8.3-4 edition of ASTM D975 applied to the (sh. 2, 3, 24, 25) emergency diesel generator fuel oil fig. 8.3-2 _ (2) reflects the revision of pg. 9.3-7, 14, 23, 41, Regulatory Guide 1.137 used for the 42, 43, 68 point by point comparison in Table tab. 9.4-8 9.5.4-3 (3) removes the comitment (sh 1, 2, 9) to introduce corrosion inhibitor on pg. 9.4-75, 84, the suction side of the plant 85, 86, 87, 88, 89, heating system hot water.punps 90, 92, 93 (4) adds a requirement to use a tab. 9.4-16, 17 corrosion inhibitor in the fig. 9.5.2-1, 2 energency diesel generator cooling pg. 3A-58 water system and (5) makes numerous pg. 9.5-51 small editorial and consistency-ques. 430.19, 20, 22, related changes.
25, 32 tab. 9.5.4-3 (sh. 1, 5)85-083 pg. 3.10(N)-5 Wis change reflects the current tab. 3.10(N)-1 status of the equipment qualification data packages.85-084 tab. 3.2-1 (sh. 7) Wis changes the safety evaluation of the fuel transfer system conveyor controls.85-085 pg. 7.5-11 This change corrects some tab. 7.5-1(sh. 1, 2) inconsistencies between table 7.5-1 tab. 9.5A-1(sh. 5) and appendix 7A, corrects an incorrect USAR cross-reference, and notes that simultaneous fires (in the context of APCSB 9.5-1, App A) are not a concern to WCGS.85-086 pg. 6.2-45 m is change allows the use of small amounts of anti-sweet fiberglass insulation inside containment.
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Attachment to Jet 87-0063 Pbrch 11, 1987
, paga 11 USAR CHANGE REQUESTS Wolf Creek Affected Change Request Portion Description of Change 85-089 FPP-6 This adds a requirement to critique a randomly selected fire drill every three years.85-090 pg. 1.2-1, 2, 3, 4, This change: (1) removes reference 5, 18, 22 to the other SNUPPS units, pg. 10.1-2 (2) corrects cross references, fig. 10.1-1 (3) establishes consistency pg. 10.2-2 ques. 430,41 internal to the USAR and (4) makes other minor editorial changes.
pg. 10.4-31, 36, 44, 45, 47, 62 85-091 tab. 15.7-4, 6, 8 This change: (1) corrects the PRT tab. 15A-2 cooling node valve configuration pg. 12.1-1, 3, 4, 7, 8 (2) corrects the sensitivity of the post accident sample room radiation tab. 11.lA-5 monitor (3) adds radiation monitors pg. 11.4-15 SD-RE-47 to table 12.3-5, and (4) pg. 11.5-1, 2, 5, 7, makes other minor editorial 8, 9, 11, 12, 14, changes.
15, 16 pg. 12.3-18, 20, 21, 23 pg. 11.2-10 tab. 12.3-4 85-092 pg. 18.1-5 This revises the responsibilities of the Duty Call Technical Advisor during an emergency.86-001 pg. 6.6-1, 2, 3, 4, 5 This change reflects the ASME codes pg. 5.2-26, 31, 32 which are used for inservice inspection.86-002 pg. 13.3-1 This change removes the WCGS Radiological thergency Response Plan from the USAR.
Attachment to hN 87-0063 March 11, 1987
, pags 12 USAR CHANGE REQUESTS Wolf Creek Affected Change Request Portion Description of Change 86-003 pg. 9.5B-5, 6 This change clarifies the USAR commitmant concerning cable qualification per IEEE-383-1974 for lighting, fire protection, comunication, and specialty cables and deletes the table of typical insulation types.86-004 pg. 3A-28, 45 This change: (1) reflects that l
pg. 9.4-71 only Callaway performed the remote shutdown test (2) references the Technical Specifications with regard to Regulatory Guide 1.108 conpliance and (3) revises the containnent pressure upper limit to be consistent with the Technical Specifications.86-005 pg. 8.3-29, 34, Exemptions from physical separation criteria are identified and l
35, 36 l justified.86-008 pg. 10.2-8, 9 Wis change: (1) corrects the tab. 10.1-1 description of the main turbino pg. 10.2-13 overspeed protection system l tab. 7A-3 (2) corrects the main turbine l
generator rating in Table 10.1-1, and (3) removes a reference to main stop and control valve maintenance platforms to establish consistency with design documents.86-009 pg. FPP-1, 2, 4, 6, This change revises the Fire 7, 8 Protection Plan to (1) reduce the adninistrative work load on the 3 dhift Supervisor by revising the I ignition source permit system '
(2) clarify fire brigade refresher i training and (3) change fire )
protection specialist responsibilities. )
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Att:chment to *vN.87-0063 March 11, 1987
. pags 13 USAR CHANGE REQUESTS Wolf Creek Affected Change Request Portion Description of Change 86-010 pg. 3.9 (B)-17 M is change clarifies the in-situ valve inspection done as part of the operational qualification for the active safety relief valves.86-012 pg. 1.2-1, 2 mis change updates the population pg. 2.1-6, 7, 8, 10, figures in the areas surrounding 11 M'GS.
tab. 2.1-1 86-013 sect. 17.2 Wis :hange contains the 1986 annual submittal of changes to the WCGS aperating quality program.
Wesce changes were sent to tha NE in FiLNE 86-041.86-014 tab. 3.11(B)-10 These changes bring the table into agreement with the EQ Equipment List - Table 3.11(B)-3. Table 3.11(B)-10 is based on NRC question 270.2.86-018 sect. 3.ll(B) This section has been conpletely revised to incorporate the information in the SNUPPS NUREG-0588 submittal transmitted by SLNRC 86-002.86-019 sect. 15.1.6 This change updates references and l sect. 15.2.8.2 assunptions used in the analyses.
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1 Attrchnent to WM 87-0063 March 11, 1987 l
. page 14 USAR CHANGE REQUESTS Wolf Creek Affected Chance Request Portion Description of Change l
l 86-021 fig.5.1-1(sh. 4) mis change added a seal table l drain system in accordance with a l
_ plant design change.
I 86-022 fig. 9.4-4 (sh. 2) This change added a dryer to the l sampling lab HVAC air handling l unit.
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86-023 pg. 3.9 (B)-21 his change updated PJmp and valve Test information to conform to current program requirenents. I 86-024 pg. 3.10 (B)-4, 5 This change revised Section 3.10(B) tab. 3.10(B)-1 to eliminate qualification details from Table 3.10(B)-1 and to note that details are available in equipment files.86-025 tab. 6.3-5(sh. 3) These tables were revised to tab. 5.4A-3 (sh. 3) incorporate as-built flow rates.86-026 pg. 6.3-14 The description of accumulator check valve testing revised to note that Technical Specifications provide test requirements.
J 86-028 tab. 6.2.2-9, Note 5 Note 5 clarifies the assunptions
, used in the sump screen approach l l velocity calculation. l l
86-029 pg. 3A-41 m is change acknowledges revision 2 l of Reg. Guide 1.97. l l
httachment to WM 87-0063 March 11, 1987
, pag 2 15 USAR CHANGE REQUESTS Wolf Creek Affected Change Request Portion Description of Change 86-030 fig. 15.3-9, 10, 11, Revised figures incorporate startup 12 test data for flow coastdown.86-031 tab. 3.9 (B)-16 mis change updates active valve tab. 3.9(N)-11 lists.
{ 86-032 pg. 3B-7, 8, 10, 11, This change is an update to steam 14 tunnel MSLB analysis resulting from tab. 3B-2, 3, 5 revised mass / energy released data.
fig. 3B-4 (sh. 1, 2, 5, 6) 1 I 86-033 pg. 3.6-5, 13, 20 This change updates pipe break tab. 3.6-3 (sh. 1-73) analysis to as-built conditions.
3 fig. 3.6-1 (sh. 9-12, i
16, 17, 21, 24-27, 40, 49) fig. 3.6-3 86-034 tab. 3.6-6 W is change revises hazards j analysis flood elevations.
1 j 86-035 pg. 3.9(N)-20 This revision provides proper tenperature for Steam Generator i tube visual leakage check.
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86-036 pg. 9.4-91 This change incorporates a design fig. 9.4-9(sh.1) change which removes 2 pressure switches in the plant heating system.86-037 tab. 7.3-14 (sh. 2) mis change updates Feedwater Isolation Signal inputs for conpleteness and consistency with other USAR information.
I 86-038 pg. 7.3-20, 21, 23 Mis change corrects Turbine-Driven Auxiliary Feedwater Ptmp steam supply valve design description.
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Attachment to WM 87-0063 March 11, 1987 pag 2 16 USAR CHANGE REQUESTS Wolf Creek Affected Change Request Portion Description of Change 86-039 pg. 9.5B-1, 169, 171 This change incorporates a reference to the latest control room fire hazards analysis.
4 86-040 tab. 9. 58-2 (sh. 6, ' This change makes the safe shutdown 7, 8, 9, 10, 11, list consistent with T3.11(B)-3.
12, 16, 17, 19, 20) l 86-041 fig. 18.2-5, 6 This change corrects errors in l radiation zone identification.86-042 pg. 9.4-70, 71 This change incorporates plans for containment entry.86-043 pg. 6.2-66 This chango adds containnent fig. 6.2.4-1 penetration data for a new system (sh. 69b) (breathing air) added by a design change.86-044 pg. 2.2-18 This change discusses locations t pg. 9.2-5 where chlorine is stored at WCGS.
!86-045 pg. 11.4-9 This change describes the j
fig. 1.2-3 capability for connecting a mobile
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fig. 9.3-1 (sh. 2) vendor solidification system.
fig. 11.4-1 (sh. 1)86-047 pg. 3.2-1, 2, 3, 4 This change incorporates editorial i tab. 3.2-1 (all sh.) revisions and revisions. required tab. 3.2-2 (sh. 2) for consistency.86-048 pg. 3.9 (N)-20 This change updates the as-built pg. 5.2-9 facility description and nakes tab. 5.3-2 editorial changes.
pg. 9.1-30, 32, 34, j 43, 49, 50, 53 '
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Attachment to Mi 87-0063 March 11, 1987 page 17 USAR CHANGE REQUESTS Wolf Creek Affected -
Change Request Portion Description of Chance 86-049 pg. 7.7-15 This change reflects a design change affecting the alarm program for normal shutdown bank manipulations.86-050 sect. 13.2 This change involves a revision of training information to remove superseded information and reflect current practice.86-051 tab. 3.ll(B)-1 Wese chanjes make the tables (sh. 1, 2) consistent with information tab. 3.ll(B)-2 previously subnitted in the SNUPPS (sh. 1, 2, 3, 4) NUREG-0588 Subnittal. Also some tab. 3. ll(B)-3 changes are made for clarification.
(all sh. and notes)86-052 tab. 1.1-1(sh. 4) This change adds information pg. 9.4-1, 3, 4, 5, regarding the SAS room air 7, 11, 12 conditioning system.
tab. 9.4-4 (sh. 6) 8'i-053 fig. 11.3-1 (sh. 1) W is change documents a design change to the gaseous radwaste systen.86-054 tab. 13.1-1 mis change revises the license requirements for the Superintendent of Operations.86-056 pg. 3A-60 This change adds Wolf Creek's position on Regulatory Guide 1.149 to Appendix 3A.86-058 pg. 15.4-25, 26, 27, W is change updates the boron 28, 29 dilution analysis for cycle 2.86-062 pg. 3A-60 Wis change states the use of code pg. 5.4-20 cases N-401, 402 per Regulatory Guide 1.147.
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Attrchment to M4 87-0063 March 11, 1987
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., USAR CHANGE REQUESTS Wolf Creek Affected Change Request Portion Description of Change 86-063 pg. 9.1-45 mese changes were made to be pg. 9.2-42 consistent with Technical pg. 10.4-48 Specifications. :
- I 86-064 flg. 9.5.7-1 M is change reflects the as-built 4
(sh. 1, 2) design of the Auxiliary Lube 011 System.
l 86-066 pg. 4.2-39 This change clarifies fuel rod clad non-destructive examination i methods.
l 86-068 tab. 6.3-5(sh. 2) This change deletes the FEMA for valves 8837A, B.86-069 sect. 17.2 mis section is updated to reflect organization (WCNOC) changes and to be consistent with Technical Specifications. We remainder of the USAR reflects the organization in effect September, 1986. Section 17 is more up to date since it is considered part of the operating Quality program.
i 86-070 tab. 15.4-1 %e change deletes superseded i
I (sh. 2, 3) information on the boron dilution accidents resulting from a revised analysis.86-073 fig. 4.2-2, 3, 9, 11, his change revises fuel bundle / rod 13, 14, 15 dimensions for cycle 2 fuel and notes that these are typical dimensions.
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Attachment to WM 87-0063 March 11, 1987
. page 19 USAR CHANGE REQUESTS Wolf Creek Affected Change Request Portion Description of Change 86-075 tab. 4.1-2 (sh. 2, 3) This change reflects the use of ANC pg. 4.3-27, 42, 48, in the cycle 2 design.
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j 86-076 tab. 9. 5. A-1 This change deletes superseded (sh. 20, 21) information.86-078 pg. 4.3-37 A correction is made regarding rod withdrawal limits applicable to flrst core.
)86-079 pg. 4.3-19 This change corrects an error (-10 vs. +10) in axial power target valves.86-080 sect. 17.2.11.2 This change reflects quality l 1
program clarifications requestel by the NRC. i l
86-081 pg. 17.2-13, 16, l This change notes that purchasing -
- 20, 24 is controlled by Material Managenent.
,86-082 pg. 17.2-53 This change reflects organization j changes, i.e., the V.P. Quality 4
reports to WCNOC President and CEO.
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] 86-083 pg. 17.2-54 This change corrects a typographical error.86-085 pg. 11.4-2, 3, 5, This change describes the bulk i 10, 11 waste handling station and makes minor changes to the description of waste handling.
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Attactrnent to
- 87-0063 March 11, 1987 page 20 USAR CHAPKIE REQUESTS Wolf Creek Affected Change Request Portion Description of Change 86-086 pg. 15.7-13, 14 mis change updated the fuel tab.15.7-2 (sh, 3) handling accident in contairinent tab. 15.7-7, 8 analysis.
86-088- ' pg.-9.1-72 Mis change deletes redundant requirenents.86-090 pg. 12.1-2, 3, 6 Mis change is an update of chapter pg. 12.3-7 ,8 ,10, 12 to reflect current plant 11, 39, 40 procedures, changes in terminology, tab. 12.3-3 the use of water cans instead of pg. 12.4-3 bags, the lab equipnent currently tab. 12.4-1 in use, changes to maintain (sh. 2, 4) cor.sistency with Technical tab. 12.4-12 Specifications and other USAR (sh. 2) Sections and to correct minor errors or clarify text.86-091 tab. 9.4-10 (sh. 5) mis change corrects the flowrate of one unit heater.86-093 fig. 17.2-1 M is change revises the hierarchy of controlled manuals.86-095 pg. 5.2-31 Wis change updates ASME Section XI visual exanination techniques used.86-097 pg. 6.3-10 Wis change clarifies that the BIT is analyzed for 9 ppm.86-098 pg. 6.3-6 Mis change clarifies the voltane of the latST.
Attcchment to WM 87-0063 March 11, 1987 page 21 USAR CHANGE REQUESTS Wolf Creek Affected Change Requast Portion Description of Change 86-100 pg. 17.2-3 This change references the Nuclear Department Policy Manual for special scope guidance. It contains a more couplete program listing.86-101 pg. 17.2-15, 16, his change updates the procurenent 24, 25 information to reflect current organization and practice.86-102 pg. 12.2-4 Mis change puts the post-accident sanpling dose rate to the operator in proper units. Wis information was formerly in the response to NRC question 331.3.86-103 pg. 11.3-8, 9 This change removes the atmospheric tab. 11.3-3 dispersion information and references instead the section 2.3 dispersion data. The results of a 1986 pathway survey are discitssed.86-104 pg. 11.3-8 This change removes duplicate information.86-107 tab. 9.5.4-3 (sh. 5) We table has been modified to be consistent with Technical Specifications for diesel fuel oil sangling.86-108 pg. 5.2-12 This change provides consistency with Technical Specification for lockout of accunulators and charging pu ps during cooldown.86-109 pg. 6.1-7 W im change notes that the 30 pg. 6.5-4, 5, 6 weight percent solution in the NaOH Addition Tank is a nominal concentration.
Attachment to Mi 87-0063 March 11, 1987 i
. page 22 USAR CHANGE REQUESTS Wolf Creek Affected Change Request Portion Description of Change i 1
86-110 pg. 7.7-11 Axial flux deviation alarm description has been updated to agree with Technical Specifications. l 86-111 tab. S.4A-1 (sh.10) M is change clarifies that the pressurizer heaters are electronically non-IE. Bis is consistent with Table 3.2.86-113 pg. 6.2-47 The description of the Refueling pg. 6.3-4 Water Storage Tank level signal for BOCS automatic switchover has been l revised to be consistent with 1 i,
Technical Specifications.86-114 pg. 9.4-30 Clarifies the sewage treatment process.86-115 Chapter 18 This chapter was updated to reflect the latest action on these issues.86-116 fig. 7.2-1 Revise figure titles to incorporate fig. 8.2-3 doctanent numbers and revisions fig. 8.2-4 fig. 10.4-2, 3 l
86-117 pg. 2.3-36 Wis change updates information provided on the Wolf Creek fog monitoring program.
l 86-120 tab. 2.1-2, 3, 4, This change relects 1980 census t
5, 8 data.
fig. 2.1-10, 16, 21 86-121 sect. 13.1 tis change reflects the September l 1986 organization. l l
87-001 sect. 2.2 Wis change updates information concerning industry facilities near Wolf Creek and revises population j statistics.
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e Attachnent to WM 87-0063 March 11, 1987
, page 23 USAR CHANGE REQUESTS Wolf Creek Affected Change Request Portion Description of Change 87-002 sect. 2.2.1.2.4.1 This change adds the ESW Pumphouse sect. 2.2.3.1.3 Chlorine storage location and sect. 2.2.3.1.7 revises the chlorine accident analysis to reference the new storage location.87-003 sect. 15.8 'Ihis change updates a discussion concerning anticipated transients without scram.
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w DISTRIBUTION CODE: USCO(
BOX 1 of 2 CONTAINS VOLUMES 1 through 7 BOX 2 of 2 CONTAINS VOLUMES 8 through 14 IF DAMAGED OR LOST, PLEASE RETURN TO:
WCNOC MSDC-WCGS BOX 411 BURLINGTON, KANSAS 66839 I
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