ML20236K488
| ML20236K488 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/02/1987 |
| From: | Shelton D TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML20236K470 | List: |
| References | |
| 1407, NUDOCS 8711090243 | |
| Download: ML20236K488 (20) | |
Text
Dockst No. 50-346 License No. NPF-3 Serial No. 1407 Enclosure I
i APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE NO. NPF-3 FOR DAVIS-BESSE NUCLEAR POWER STATION UNIT NO. 1 Attached are requested changes to the Davis-Besse Nuclear Power Station, Unit No. 1 Facility Operating License No. NPF-3.
Also included are the Safety Evaluation and Significant Hazards Consideration.
The proposed changes (submitted under cover letter Serial No. 1407) concern:
Appendix A Technical Specifications and Bases.
By:
D. C. Shelton, Vice President, Nuclear l
Sworn and subscribed before me this 2nd day of November, 1987.
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Notary Public, State of Ohio My commission expires d /t[ h/
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Dockot No,'50-346--
License No..NPF-3 Serial No. 1407 Enclosure The following information is provided to support issuance of-the.
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- _ requested changes:to the Davis-Besse. Nuclear Power Station, Unit-No. 1 Operating'. License No. NPF-3, Appendix A, Technical Specifications.
A.
- Time Required to Implement
- This change will be implemented within 30 days.following NRC issuance of the License Amendment.:
B.
Reason for Change (FCR No. 87-0124): Revise Appendix A Technical ~-
Specifications and Bases to correct typographical and administrative-
il errors.
C.
Safety l Evaluation:
See attached. Safety Evaluation (Attachment.'
.)
No. 1).
d D.
Significant Hazards Consideration:
See attached Significant Hazards Consideration (Attachment No.'2).
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Docket No. 50-346 License No. NPF-3 Serial No. 1407 Page 1 SAFETY EVALUATION DESCRIPTION OF THE PROPOSED ACTIVITY The purpose of this Safety Evaluation is to review proposed changes to the Davis-Besse Nuclear Power Station Unit No. 1 Operating License, Appendix A Technical Specifications and Bases.
The proposed changes involve correcting typographical and administrative errors in the Tech-nical Specifications and Bases.
PROPOSED AMENDMENT REQUEST DISCUSSION The proposed License Amendment Request revises the following Davis-Besse Nuclear Power Station, Unit No. 1 Operating License, Appendix A Technical Specifications and Bases:
Index, page IV - Corrects heading; changes " Steam and Feed Rupture Control System" to " Steam and Feedwater Rupture Control System".
This is to ensure consistency within the Technical Specifications. This is a typographical correction.
Index, page IV - Adds " Radioactive Gaueous Effluent Monitoring Instrumen-tation 3/4 3-62".
This Technical Specification was added in Amendment No. 86, the Radiological Environmental Technical Specifications (RETS) submittal; however, the index was not updated to reflect this change.
Therefore, this is an administrative change.
i Index, page VI - Corrects heading; changes 3/4.6.5 " SECONDARY CONTAINMENT" to " SHIELD BUILDING". This is to ensure consistency within the Technical l
Specifications. This is a typographical correction.
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Index, page VII - Deletes " Secondary Water Chemistry..
3/4 7-10".
l Amendment No. 47 deleted the Technical Specification relating to secondary i
water chemistry (Section 3/4.7.1.6) and added License Condition 2.C. (5) j regarding implementation of a secondary water chemistry monitoring pro-
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gram; however, the index was not updated to reflect this change. There-fore, this is an administrative change.
i Index, page VII - Corrects heading; changes 3/4.7.7 " HYDRAULIC-SNUBBERS" to l
" SNUBBERS". Amendment No. 94 deleted the word " HYDRAULIC" to add require-j ments for mechanical snubber operability and testing; however, the index j
was not' updated to reflect this change. Therefore, this is an administrative j
change.
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Bases Index, page XII - Corrects heading; changes 3/4.7.7 " HYDRAULIC SNUBBERS" to " SNUBBERS". Amendment No. 94 deleted the word " HYDRAULIC" to add requirements for mechanical snubber operability and testing; however, j
the Bases index.was not updated to reflect this change. Therefore, this j
is an administrative change.
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Docket No. 50-346 License No. NPF-3 Serial No. 1407 Page 2 i
Index, page XV - Adds " Facility Staff Overtime..
6-4a".
Amendment No. 88 added Section 6.2.3, Facility Staff Overtime to limit facility staff working I
hours; however, the index was not updated to reflect this change. There-fore, this is an administrative change.
l Index, page XV - Changes the Authority Section page reference from "6-7" to "6-8".
In Amendment No, 86, additional responsibilities were added to Section 6.5.1.6.
This forced the Authority Section onto the next page, 6-8; however, the index was not updated to reflect this change. Therefore, this is an administrative change.
j Index, page XVI - Changes the Authority Section page reference from "6-11" to 6-12".
In Amendment No. 86, additions were added to Section 6.5.2.8.-
This forced the Authority Section onto the next page, 6-12; however, the index was not updated to reflect this change. Therefore, this is an i
administrative change.
Index, page XVI - Changes 6.6 " REPORTABLE OCCURRENCE ACTION" to " REPORT-ABLE EVENT ACTION". This Technical Specification was amended in Amendment No. 93, at the request of the NRC (Generic Letter No. 83-43), to incorporate j
the revision to 10 CFR 50.72, Immediate Notification Requirements, and the addition of 10 CFR 50.73, Licensee Event Report System; however, the index j
was not updated to reflect this change. Therefore, this is an administra-tive change.
Index, page XVI - Changes 6.9.1 " ROUTINE REPORTS AND REPORTABLE OCCUR-
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RENCES..
6-14" to " ROUTINE REPORTS..
6-14a".
This Technical Specific-l ation was amended in Amendment No. 93 at the request of the NRC (Generic j
Letter No. 83-43) to incorporate the revision to 10 CFR 50.72, Immediate j
Notification Requirements, and the addition of 10 CFR 50.73, License Event Report System; however, the index was not updated to reflect this change.
l Also, Amendment No. 51 added Section 6.8.4 forcing the Routine Reports Section onto the next page, 6-14a.
Therefore, these are administrative i
changes.
t Index, page XVI - Changes the Record Retention Secticn page reference from l
"6-18" to "6-18a".
In Amendment No. 86, additional reports were added to l
Section 6.9.2.
This forced the Record Retention Section onto the next page, 6-18a; however, the index.was not updated to reflect this change.
Therefore, this is an administrative change.
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Index, page XVI - Adds "6.14 PROCESS CONTROL PROGRAM (PCP)... 6-22", "6.15 l
OFFSITE DOSE CALCULATION MANUAL (0DCM)... 6-22", and "6.16 MAJOR CHANGES TO RADI0 ACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS..
6-23".
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These Technical Specification Sections were added in Amendment No. 86 to
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ensure compliance with 10 CFR 50.36a; however, the index was not updated l
to reflect this change. Therefwe,-these are administrative changes.
i Page 3/4 0 Corrects the misspelled word; changes " SURVEIL ANCE" to
" SURVEILLANCE". This is a typographical correction.
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Docket No. 50-346
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License No. NPF-3 Serial No. 1407 Page 3 i
4.1.2.4 (page 3/4 1-10) - Deletes the unnecessarily repeated word "at".
This is a typographical correction.
4.1.3.1.1 (page 3/4 1-20) - Corrects tbe incomplete word; changes "Faul" to " Fault". This is to ensure consistency within the Surveillance Requirements. This is a typographical correction.
Page 3/4 2 Changes " exception" to " Exception".
This typographical correction is to ensure consistency within the Technical Specifications.
4.2.3.1 (page 3/4 2-8) - Adds the subscript "H"; changes "F " to "F This is a typographical correction.
3.2.4 (page 3/4 2-10) - Adds " ACTION:
(Continued)" to the tcp of the page. The Action Statements of Technical Specification.3,2.4 start on page 3/4 2-9 and are continued onto page 3/4 2-10.
This is a typographical correction.
Table 3.3-2 (page 3/4 2-12) - Changes " Quadrant Power Tilt" to " QUADRANT POWER TILT".
In the Technical Specifications, defined terms appear in capitalized type; QUADRANT POWER TILT is a defined term. This is'a typo-graphical correction.
Table 3.3-1 (page 3/4 3-4) - Changes " RATED RATED POWER" to." RATED TIERMAL' POWER" in ACTION 2.c.
This is to ensure the correct intent of'the Action Statement in Table 3.3-1.
This is a typographical correction.
Table 3.3-1 (page 3/4 3-4) - Changes "TIERMAL Power" to " THERMAL POWER" in ACTION 4.
In the Technical Specifications, defined terms appear in capitalized type; TIERMAL POWER is a defined term.
This is a typographical correction.
Table 3.3-1 (page 3/4 3-5) - Adds the word "up" in ACTION 7.b. so it reads
"...may be bypassed for up to 30 minutes...".
This is to ensure the correct intent of the Action Statement in Table 3.3-1 and make-the Action Statements-consistent within Table 3.3.-l.
This is a typographical correction.
Table 4.3-1 (page 3/4 3-8) - Deletes the footnote reference "***" and the i
footnote "*** - Eighteen-month surveillance test due in March 1982 delayed until March 31, 1982" which has expired. These are administrative changes.
Table 3.3-3 (page 3/4 3-11) - Changes " FUNCTION UNIT" to " FUNCTIONAL UNIT".
This is to ensure the correct intent of the table headings and make them-consistent in Table 3.3-3.
This is a typographical correction.
Table 3.3-3 (page 3/4 3-12) - Changes "startup" to "STARTUP" and " power operation" to " POWER OPERATION" in ACTION 9.
In the Technical Specif--
ications, defined terms appear in capitalized type; both STARTUP and POWER OPERATION are defined terms. These are typographical corrections.
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Docket No. 50-346-
- l License No. NPF-3 y
(l Serial No. 1407 i
-Attachment 1 Page 4 1
Table 4.3-2 (page 3/4 3-21) - Deletes the footn6te reference "*" and the footnote "* Eighteen month surveillance test due in March 1982 delayed until March 31, 1982" which has expired.
These are administrative changes.
Table 4.3-2 (page 3/4 3-22) - Adds "(Continued)" after the Table Number on D
i page 3/4 3-22.
Table 4.3-2 starti on page 3/4 3-21 and is continued onto page 3/4.3-22. This is a typographical correction.
Table 3.3-11 (page 3/4 3-27) - Ch;snges "startup" to "STARTUP" and " power operation" to " POWER OPERATION" in ACTION 13.
In the Technical Specifi-cations, defined terms appear in capitalized type; both STARTUP.and POWER OPERATION are defined terms. These are typographical corrections.
Table 4.3-11 (page 3/4 3-30) - Deletes the foot; note reference "+" and the footnote "+The surveillance period for Steam Line Pressure-Low Instru-ment is extended to 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br />, September 16, 1982" which has expired.
These are administrative changes.
3.3.2.3 (page 3/4 3-30a) - Changes the three references from Table "3.3-15" to Table "3.3-17".
(See below change to Table 3.3-15).
These are adminis-trative changes.
'i 4.3.2.3 (page 3/4 3-30a) - Changes the reference from Table "4.3-15" to 1
"4.3-17".
(See below change to Table 4.3-15.)
This is an. administrative j
change.
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Table 3.3-15, Anticipatory Reactor Trip System Instrumentation (page 3/4 1
3-30b) - Changes the Table Number'from "3.3-15" to "3.3-17.".
Currently,
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Technical Specification Section 3/4.3, Instrumentation, contains two j
unique tables with the same table number,.(Table 3.3-15, Radioactive
.j Liquid Effluent Monitoring Instrumentation, page 3/4.3-58,and Table i
3.3-15, Anticipatory Reactor Trip System Instrumentation, page 3/4 3-30b).
j This administrative change would give each table a unique' number.
Page 3/4 3-30b - Adds-Amendment No. "73" to the bottom of the page. This l
page was issued in Amendment No. 73; however, it was issued without l
reference to Amendment No. 73.
Therefore, this is a typographical' l
correction.
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Table 3.3-15 (page 3/4 3-30c)
Changes the Table Number from "3.3-15" to.
"3.3-17".
Table 3.3-15 starts on page'3/4 3'30b andtis continued onto page 3/4 3-30c.
See above change to Table 3.3-15.
This is an.adminis-trative change, q
1 Table 3.3-15 (page 3/4L3-30c)
Adds "/or" to ACTION 18; changes "STARTUP 1
and POWER OPERATION" to "STARTUP and/or POWER OPERATION" to ensure consis-tency within the Technical Specifications. Thi.s addition is also consis-tent with the B&W Standard Technical Specifications, NUREG-0103,: Revision..
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Reference:
Technical Specification Table 3.3-1, ACTION 7).
This is a i
typographical correction.
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Docket No. 50-346 License No. NPF-3 Serial No. 1407 Page 5 i
Table 4.3-15, Anticipatory Reactor Trip' System Instrumentation Surveil-lance Requirements, (page 3/4 3-30d) - Changes the Table Number from "4.3-15"-
j to "4.3-17".
Currently, Technical Specification.Section 3.4.3, Instru--
j mentation, contains two unique tablis with the.same table nunber, (Table e
4.3-15, Radioactive. Gaseous Effluent'. Monitoring Instrumentation, page 3/4 3-58 and Table 4.3-15, Anticipatory Reactor Trip System Instrumentation Surveil-la. ice Requirements, page 3/4 3-30d). This administrative change would give each table a unique number.
1 Table 4.3-6 (page 3/4 3-45) - Deletes the. footnote reference "*" and the footnote "18 month surveillance test due May 17, 1983, may be delayed until 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> September 17, 1983" which has expired. These are administrative changes.
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l Table 4.3-10 (page 3/4 3-49) - Deletes the footnote reference "*" and the i
footnote "*18 month surveillance test due'May 17, 1983, may be delayed until 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> September 17, 1983" which has expired.
These are admin-
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istrative changes, j
i 3.3.3.7 (page 3/4 3-51) - Adds the word " MODES"; changes " APPLICABILITY:
1, 2, 3 and 4" to " APPLICABILITY: MODES 1, 2, 3 and 4".
This is to ensure consistency within the Technical Specifications.
This is a typo-I graphical correction.
l Table 3.3-14 (page 3/4 3-54) - Adds the table heading " Table 3.3-14 (Continued)" to the top of the page. Table 3.3-14 starts on page 3/4 3-53 and is continued onto page 3/4 3-54.
Currently, there is no heading on i
page 3/4 3-54.
This is a typographical' correction.
Table 3.3-14 (page 3/4 3-55) - Adds the table heading " Table 3.3-14 (Continued)" to the top of the gage.
Table 3.3-14 starts on page 3/4 3-53 and is continued onto page 3/4 3-55.
Currently, there is no heading on page 3/4 3-55.
This is a typographical correction.
Table 3.3-14 (page 3/4 3-56) - Adds the table heading " Table 3.3-14
'i gontinued)" to the top of the page. Table 3.3-14 starts on page 3/4 3-53 and is continued onto page 3/4 3-56.
Currently, there is no heading on page 3/4 3-56.
This is typographical correction.
Page 3/4 4 Modifies two Technical Specification Section Numbers; changes "4.4.1.1" to "4.4.1.1.1" and similarly "4.4.1.2" to "4.4.1.1.2".
This is to ensure consistency within the Tecitnical Specifications (see Surveillance Requirements of Technical Specification 3.4.1.2, numbered 4.4.1.2.1, 4.4.1.2.2 and 4.4.1.2.3 respect vely).
These are administrative i
changes.
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Page 3/4 4-2a - Adds " Amendment No. 38" to the bottom of the page.
In:
4 Amendment No. 38, fad 4ttions/mo?gicat. ions were made to the decay heat
< removal-Technical
- Specification M These additions / modifications included adding page-3/4 4-?.a and the Surveillance Requirements on that page.
However, this page was inadg/rtently issued without the rMctence to -
Amendment No. 38 L, qThereford,.this is a. typographical corr' ction.
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Figure 3.4.2-a-(psge3/44-4a).-Corrects.t$e(figuyenMber; changes-N'
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- 3.4.2-a" to "3.4-2a".
This is'to ensure iodsisten Specifications;(Thfs'isa;typographicalicorrectiop]ypithintheTechnical'
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u Figure ').4. 2 6 (page - 3/4 l44b)!- Cod,, c,ts the figure" number; changes e
"3.4.2-F to "3 4-2b".
Thrs is to wure consistency within. the Technical y
Specificappa. ' This is a typographical correction.
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Page of4'4 5 - Cortabts the incompleth page number;.changeg "/4 4-5" to:.
"3/4S3".OThisistoensureconsist'ncywithintheTechnicalSpecifica','
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khbisatypographicalcorrection.
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3.4.6(2 (page 3/4 4-15) - Changes " power operation" to." POWER OPERATION" A
in ApTION c.
In the Technical Specifications, defined terms appear in Jerpitalized type; POWER OPERATION is a defined term.. This-is a typogra-
/p, dical correction.
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r dl.4'.U2.1 - (page 3/4 4-16) - Corrects wording of Arfftop Jtatement; changes f
sh. t D.",COU(rob,1DLEAKAGEtothereactorcoolantpumpsedsto..."to
/ '/d,CONERCELED LEAKAGE from the reactor coolant pump' seals to...".
This is consistent with the definition of Controlled Leakage which is defined-i" as being the-leakage "from" their9setor coolant pump, seals, 'This is also
.consistents/ith Base's 3/4.4.6.2[ Operational Leakage, which restricts operation with a total RCS leakage "from" all RC pump seals in excess of 10 QPM to the Controlled Leakage, limit of 10 GPht This is to ensure the.
correct intent of the Action Stitement. Thqrpfore, this 'is a typo-grapbfcAl correction.
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Ffgure-0.4-1 (page 3/4 4-23).- Changes " Dose Equivalent;T-131" to " DOSE 1
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EQUIVAI NT I-131".
IntheTechnicalSpecificatpns,defin6dtermsiabear.
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in capitalized type; DOSE EQUIVALENT I-}31 is,a, defined term. This'is.a t'
typographical correction.
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3.4.11.c (page 3/4 4-32)-- Corrects the valve number;; changes "RC2" to-
'9C2A".
This is a-typographical correction.
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Page 3/4 5 Adds "(Continued)", tkoj the ' top 'of the page. - The Surwillance-Requirements- (4.5.2) start on page 5-3 and areicontinued onto page J."
This is a-typographical correction.
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Docket No. 50-346 License No. NPF-3 Serial No. 1407 Page 7 Table 3.6-2 (page 3/4 6-20) - Corrects description of valve number SW1358, Penetration Number 10; changes " Containment Air Cooling Units SW Inlet Line" to " Containment Air Cooling Units SW Outlet Line".
Service water valve numbers SW1366, 1367 and 1368 are the inlet lines while SW 1356,_1357 and 1358 are the outlet lines.
This is a typographical correction.
Table 3.6-2 (page 3/4 6-20) - Corrects description of valve number DH77, l
Penetration Number 28; changes " Low Pressure trigection Line" to " Low Pressure Injection Line".
This is a typographical correction.
4.6.5.1 (page 3/4 6-29) - Deletes the two footnote references "**" and the footnote "** Eighteen month surveillance test due in March 1982 delayed j
until March 31, 1982" which has expired.
These are administrative changes.
4.7.2.1 (page 3/4 7-13) - Corrects the misspelled word; changes "coolnat" to " coolant". This is typographical correction.
4.9.12.1 (page 3/4 9-12) - Changes " Water Guage" to " water gauge".
This typographical correction is to ensure consistency within the Technical Specifications.
Page 3/4 10 Changes (in two places) "startup" to "STARTUP".
In the Technical Specifications, defined terms appear in capitalized type; STARTUP is a defined term. These are typographical corrections.
3.11.2.1 (page 3/4 11-9) - Changes " RATE (s)" to " rate (s)" in ACTION c.
In the Technical Specifications, only defined terms appear in capitalized type; rate (s) is not a defined term.
This is a typographical correction.
3.12.1 (page 3/4 12-1) - Corrects the Technical Specification reference in ACTION a; changes "6.9.1.11" to "6.9.1.10".
Technical Specification 6.9.1.11 is the Semiannual Radioactive Effluent Release Report, not the desired Annual Radiological Environmental Operating Report as specified in 6.9.1.10.
Therefore, this is a typographical correction.
Page 3/4 12 Adds " ACTION:
(Continued)" to the top of the page. The ACTION statements of Technical Specification 3.12.1 start on page 3/4 12-1 and are continued onto page 3/4 12-2.
This is a typographical correction.
3.12.1 (page 3/4 12-2) - Corrects the Technical Specification reference in ACTION d; changes "6.1.1.10" to "6.9.1.10".
Technical Specification 6.9.1.10 is the desired Annual Radiological Environmental Operating Report.
There is no Technical Specification 6.1.1.10.
Therefore, this is a typo-graphica? correction.
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Docket No. 50-346 License No. NPF-3 Serial No. 1407-Page 8 Page B 3/4 Q-lb - Corrects the page number; changes "B 3/4 Q-1B" to "B 3/4 0-1b".
This is to ensure consistency within the Technical Specifications. This is a typographical correction.
Page B 3/4 3 Corrects the misspelled word; changes " test" to " tests".
1 This is a typographical correction.
l Page B 3/4 3 Corrects the misspelled word; changes "THERMANL" to
" THERMAL". This is a typographical correction.
Bases 3/4.6.1.7 (page B 3/4 6-2) - Corrects the misspelled. word; changes "occuring" to " occurring".
This is a typographical correction.
Bases 3/4.6.5.2 (page B 3/4 6-5) - Corrects the misspelled word; changes
" gage" to " gauge".
This is a typographical correction.
Bases 3/4.7.8 (page B 3/4 7-6) - Corrects the misspelled heading; changes
" CONTAMINATION" to 'CORIAMINATION". This is a typographical correction.
Bases 3/4 7.9 (page B 3/4 7-6) - Corrects the misspelled word; changes "occuring" to " occurring". This is a typographical correction.
5.6.1.1.a (page 5-5) - Corrects the misspelled word; changes "uborated"
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to "unborated".
This is a typographical correction.
DISCUSSION OF UNREVIEWED SAFETY QUESTION The proposed changes involve administrative changes and typographical corrections. Therefore, the implementation of these proposed changes would not:
Increase the probability of occurrence of an accident previously evalu-
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ated in the USAR because the accident conditions and assumptions are not J
'affected by the proposed Technical Specification and Bases changes. The proposed changes do not involve a test or experiment, or'a modification to l
a system. The proposed changes are administrative in nature and do not-increase the probability of an accident previously evaluated (10CFR50.59(a)(2)(i)).
Increase the consequences of an accident previously evaluated in the USAR because the accident conditions and assumptions are not affected by the proposed Technical Specification and Bases changes. The proposed changes do not involve a test or experiment, or a modification to a-system. The proposed changes are administrative in nature and do not increase the consequences of an accident previously evaluated (10CFR50.59(a)(2)(i)).
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Docket No. 50-346 License No. NPF-3 Serial No. 1407 I
Page 9 i
Increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the USAR because the proposed changes do not involve a test or experiment and no station equipment is being modified. The proposed changes are administrative in nature and'do not increase the probability of occurrence of a malfunction of equipment important to safety (10CFR50.59(a)(2)(i)).
Increase the consequences of a malfunction of equipment important to safety previously evaluated in the USAR because the proposed changes do not involve a test or experiment and no station equipment is being-modified. The proposed changes are administrative in nature and dofnot increase the consequences of a malfunction of equipment important to safety (10CFR50.59(a)(2)(i)).
Create the possibility for an accident of a different type than any evaluated previously in the USAR because the accident conditions and assumptions are not affected by the proposed Technical Specification and Bases changes. The proposed changes do not involve a test or experiment, or a modification to a system and do not affect any plant equipment or oper-ational procedures which could impact the probability of an cccident. The proposed changes are administrative in nature and involve no accident scenario. On matters related to nuclear safety, all accidents are bounded by previous analysis and no new accidents are involved (10CFR50.59(a)(2)(ii)).
Create the possibility for a malfunction of a different type than any evaluated previously in the USAR because no station equipment is being modified by the proposed Technical Specification and Bases changes. The proposed changes do not involve a test or experiment, or a modification to a system and do not a~#ect any plant equipment or operational procedures which could impact the p; ;oability of a malfunction. The changes are administrative in nature and involve no malfunction scenario (10CFR50.59(a)(2)(ii)).
Reduce any margin of safety as defined in the basis for any Technical Specification because the amendment does not affect any operating prac-tices or limits nor any equipment or system important to safety. The proposed changes are administrative in nature and will not reduce the margin of safety (10CFR50.59(a)(2)(iii)).
CONCLUSION Based on the above, it is concluded that the proposed Technical Specifica-tion and Bases changes do not constitute an unreviewed safety question.
Docket No. 50-346 License No. NPF-3 Serial No. 1407 Page 1 SIGNIFICANT HAZARDS CONSIDERATION-DESCRIPTION OF THE PROPOSED ACTIVITY The purpose of this. License Amendment Request is to review proposed changes to the Davis-Besse Nuclear Power Station Unit No. 1 Operating License, Appendix A Technical Specifications and Bases. The proposed changes involve correcting typographical and administrative errors in the Technical Specifications and Bases.
PROPOSED AMENDMENT REQUEST DISCUSSION The proposed License Amendment Request' revises the following Davis-Besse Nuclear Power Station, Unit No. 1 Operating License, Appendix A Technical Specifications and Bases:
Index, page IV - Corrects heading; changes " Steam and Feed Rupture Control System" to " Steam and Feedwater Rupture Control System". This is to ensure consistency within the Technical Specifications. This is a typographical correction.
Index, page IV - Adds " Radioactive Gaseous Effluent Monitoring.Instrumen-tation 3/4 3-62".
This Technical Specif.ication was added in Amendment No. 86, the Radiological Environmental Technical Specifications (RETS) submittal; however, the index was not updated to reflect this change.
Therefore, this is an administrative change.
Index, page VI - Corrects heading; changes 3/4.6.5 " SECONDARY CONTAINMENT" to " SHIELD BUILDING". This is to ensure consistency within the Technical Specifications. This is a typographical correction, l
Index, page VII - Deletes " Secondary Water Chemistry..
3/4 7-10".
Amendment No. 47 deleted the Technical Specification relating to secondary water chemistry (Section 3/4.7.1.6) and added License Condition 2.C.(5) regarding implementation of a secondary water chemistry monitoring pro-gram; however, the index was not updated to reflect this change.. There-fore, this is an administrative change.
Index, page VII - Corrects heading; changes 3/4.7.7." HYDRAULIC SNUBBERS" to
" SNUBBERS". Amendment No. 94 delated the word " HYDRAULIC" to add require-ments for mechanical snubber operability and testing; however, the index was not updated-to reflect this change. Therefore, this is an administrative.
s change.
Bases Index, page XII - Corrects heading; changes 3/4.7.7 " HYDRAULIC SNUBBERS" to " SNUBBERS". Amendment No. 94 deleted the. word " HYDRAULIC" to add requirements for mechanical snubber operability and testing; however, the Bases index was not updated to reflect this change. Therefore, this is an administrative change.
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Docket No. 50-346 License No. NPF-3 Serial No. 1407 Page 2 l
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Index, page XV - Adds " Facility Staff Overtime..
6-4a".
Amendment No. 88 added Section 6.2.3, Facility Staff Overtime to limit facility staff working hours; however, the index was not updated to reflect this change. There-fore, this is an administrative change.
Index, page XV - Changes the Authority Section page reference from "6-7" to "6-8".
In Amendment No. 86, additional responsibilities were added to Section 6.5.1.6.
This forced.the Authority Section onto the next page, 6-8; however, the index was not updated to reflect this change. Therefore, this is an administrative change.
Index, page XVI - Changes the Authority Section page reference from "6-11" to 6-12".
In Amendment No. 86, additions were added to Section 6.5.2.8.
This forced the Authority Section onto the next page, 6-12; however, the index was not updated to reflect this change. Therefore, this is'an administrative change.
Index, page XVI - Changes 6.6 " REPORTABLE OCCURRENCE ACTION" to " REPORT-ABLE EVENT ACTION". This Technical Specification was amended in Amendment No. 93, at the request of the NRC (Generic Letter,No. 83-43), to incorporate the revision to 10 CFR 50.72, Immediate Notification Requirements, and the addition of 10 CFR 50.73, Licensee Event Renort System; however, the'index was not updated to reflect this change.
Therefore, this is an administra-tive change.
Index, page XVI - Changes 6.9.1 " ROUTINE REPORTS AND REPORTABLE OCCUR-RENCES..
6-14" to " ROUTINE REPORTS..
6-14a".
This Technical Specific-ation was amended in Amendment No. 93 at the request of the NRC (Generic Letter No. 83-43) to incorporate the revision to 10 CFR 50.72, Immediate Notification Requirements, and the addition of 10 CFR 50.73, License Event j
Report System; however, the index was not updated to reflect this change.
Also, Amendment No. 51 added Section 6.8.4 forcing ~the Routine Reports Section onto the next page, 6-14a.
Therefore, these are administrative changes.
Index, page XVI - Changes the Record Retention Section page reference from "6-18" to "6-18a".
In Amendment No. 86, additional reports were added to Section 6.9.2.
This forced the Record Retention Section onto the next page, 6-18a; however, the index was not updated to reflect this change.
Therefore, th.s is an administrative change.
Index, page XVI - Adds "6.14 PROCESS CONTROL PROGRAM (PCP)... 6-22", "6.15 0FFSITE DOSE CALCULATION MANUAL (0DCM)..
6-22", and "6.16 MAJOR CHANGES TO RADI0 ACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS..
6-23".
These Technical Specification Sections were added in' Amendment No. 86 to ensure. compliance with 10 CFR 50.36a; however, the index was not updated to reflect this change. Therefore, these are administrative changes.
Page 3/4 0 Corrects the misspelled word; changes " SURVEIL ANCE" to
" SURVEILLANCE". This is a typographical correction.
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License No. NPF-3 Serial No. 1407 Page 3 4.1.2.4 (page 3/4 1-10) - Deletes the unnecessarily repeated word "at".
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This is a typographical correction.
4.1.3.1.1 (page 3/4 1-20) - Corrects.the incomplete. word; changes "Faul" to " Fault".
This is to ensure consistency within the Surveillance Requirements. This is a typographical correction.
I Page 3/4 2 Changes " exception" to " Exception". This. typographical correction is to ensure consistency within the-Technical-Specifications.
,l 4.2.3.1 (page 3/4 2-8) - Adds the subscript "H"; changes "F " to "F This is a typographical correction.
3.2.4 (page 3/4 2-10) - Adds " ACTION:
(Continued)" to the top.of the page. The Action Statements of Technical Specification 3.2.4 start on page 3/4 2-9 and are continued onto page 3/4 2-10.
This is a typographical correction.
Table 3.3-2 (page 3/4 2-12) - Changes " Quadrant Power Tilt" to " QUADRANT POWER TILT".
In the Technical Specifications, defined terms appear in capitalized type; QUADRANT POWER TILT is a defined term. This is a typo-graphical correction.
Table 3.3-1 (page 3/4 3-4) - Changes " RATED RATED POWER" to " RATED THERMAL POWER" in ACTION 2.c.
This is to ensure the correct intent of the Action Statement in Table 3.3-1.
This is a typographical correction.
Table 3.3-1 (page 3/4 3-4) - Changes " THERMAL Power" to " THERMAL POWER" in ACTION 4.
In the Technical Specifications, defined terms appear in capitalized type; THERMAL POWER is a defined term. This is a typographical correction.
Table 3.3-1 (page 3/4 3-5) - Adds the word "up" in ACTION 7.b. so it reads
"...may be bypassed for up to 30 minutes...".
This is to ensure the correct intent of the Action Statement in Table 3.3-1 and make the Action Statements consistent within Table 3.3.-l.
This is a typographical correction.
Table 4.3-1 (page 3/4 3-8) - Deletes the footnote reference "***" and the footnote "*** - Eighteen-month surveillance test due in March 1982 delayed until March 31, 1982" which has expired. These are administrative changes.
Table 3.3-3 (page 3/4 3-11) - Changes " FUNCTION UNIT" to " FUNCTIONAL UNIT".
This is to ensure the correct intent of the table headings and make them consistent in Table 3.3-3.
This is a typographical correction.
Table 3.3-3 (page 3/4 3-12) - Changes "startup" to "STARTUP" and " power operation" to " POWER OPERATION" in ACTION 9.
In the Technical Specif-ications, defined terms appear in capitalized. type; both STARTUP and POWER OPERATION are defined terms. These are typographical corrections,
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Docket No. 50-346 License No. NPF-3
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Table 4.3-2 (page 3/4 3-21) - Deletes the footnote reference "*" and the i
footnote "* Eighteen month surveillance test due in March 1982 delayed
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until March 31, 1982" which has expired. These are administrative changes.
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Table 4.3-2 (page 3/4 3-22) - Adds "(Continued)" after the Table Number on page 3/4 3-22.
Table 4.3-2 starts on page 3/4 3-21 and is continued onto page 3/4 3-22.
This is a typographical correc+ ion.
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i Table 3.3-11 (page 3/4 3-27) - Changes "startup" to "STARTUP" and " power operation" to " POWER OPERATION" in ACTION 13.
In the Technical Specifi-cations, defined terms appear in capitalized type; both STARTUP and POWER OPERATION are defined terms. These are typographical corrections.
Table 4.3-11 (page 3/4 3-30) - Deletes the footnote reference "+" and the footnote "+The surveillance period for Steam Line Pressure-Low Instru-
-I ment is extended to 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br />, September 16, 1982" which has expired.
These are administrative changes.
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3.3.2.3 (page 3/4 3-30a) - Changes the three references from Table "3.3-15" to Table "3.3-17".
(See below change to Table 3.3-15).
These are adminis-trative changes.
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4.3.2.3 (page 3/4 3-30a) - Changes the reference from Table."4.3-15" to "4.3-17".
(See below change to Table 4.-3-15.)
This is an administrative I
change.
J Table 3.3-15, Anticipatory Reactor Trip System Instrumentation (page 3/4
)
3-30b) - Changes the Table Number from "3.3-15" to "3.3-17".
Currently, I
Technical Specification Section 3/4.3, Instrumentation, contains two unique tables with the same table number, (Table 3.3-15, Radioactive Liquid Effluent Monitoring Inst.rumentation, page 3/4 3-58 and Table 3.3-15, Anticipatory Reactor Trip System Instrumentation, page 3/4 3-30b).
This administrative change would give each table a unique number.
Page 3/4 3-30b - Adds Amendment No. "73" to the bottom of the page. This page was issued in Amendment No. 73; however, it was issued without i
reference to Amendment No. 73.
Therefore, this is a typographical correction.
Table 3.3-15 (page 3/4 3-30c) - Changes the Table. Number from "3.3-15" to "3.3-17".
Table 3.3-15 starts on page 3/4 3-30b and is continued onto page 3/4 3-30c.
See above change to Table 3.3-15..This is an adminis-trative change.
Table 3.3-15 (page 3/4 3-30c) - Adds "/or" to ACTION 18; changes "STARTUP and POWER OPERATION" to "STARTUP and/or POWER OPERATION" to ensure consis-tency within the Technical Specifications. -This addition is also consis-tent with the B&W Standard Technical Specifications, NUREG-0103, Revision 4 (
Reference:
Technical Specification Table 3'.3-1, ACTION 7).
This is a typographical correction.
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Table 4.3-15, Anticipatory Reactor Trip System Instrumentation Surveil-lance Requirements, (page 3/4 3-30d) - Changes the Table Number from "4.3-15" to "4.3-17".
Currently, Technical Specification Section 3.4.3, Instru-i mentation, contains two unique tables with the same table number, (Table j
4.3-15, Radioactive Gaseous Effluent Monitoring Instrumentation, page 3/4 3-58 and Table 4.3-15, Anticipatory Reactor Trip System Instrumentation Surveil-I lance Requirements, page 3/4 3-30d).
This administrative change would give each table a unique number.
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i Table 4.3-6 (page 3/4 3-45) - Deletes the footnote reference
'!*" and the i
footnote "18 month surveillance test due May 17, 1983, may be delayed until 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> September 17, 1983" which has expired. These are l
administrative changes.
Table 4.3-10 (page 3/4'3-49) - Deletes the footnote reference "*" and the footnote "*18 month surveillance test due May 17, 1983, may be delayed' until 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> September 17, 1983" which has expired. These are admin-
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istrative changes-J J
3.3.3.7 (page 3/4 3-51) - Adds the word " MODES"; changes " APPLICABILITY:
1, 2, 3 and 4" to " APPLICABILITY: MODES 1, 2, 3 and 4".
This is to j
ensure consistency within the Technical Specifications. This is a typo-graphical correction.
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J Table 3.3-14 (page 3/4 3-54) - Adds the table heading " Table 3.3-14
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(Continued)" to the top of the page. Table 3.3-14 starts on page 3/4 3-53
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and is continued onto page 3/4 3-54.
Currently, there is no heading on 1
page 3/4 3-54.
This is a typographical correction.
I Table 3.3-14 (page 3/4 3-55) - Adds the. table heading " Table 3.3-14
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(Continued)" to the top of the page.
Table 3.3-14 starts on page 3/4 3-53 and is continued onto page 3/4 3-55.
Currently, there is no heading on page 3/4 3-55.
This is a typographical correction.
1 Table 3.3-14 (page 3/4 3-56) - Adds the table heading " Table 3.3-14.
(Continued)" to the top of.the page. Table 3.3-14 starts on page 3/4 3-53 and is continued onto page 3/4 3-56.
Currently, there is no heading on page 3/4 3-56.
This is typographical correction.
Page 3/4 4 Modifies two Technical Specification Section Numbers; changes "4.4.1.1" to "4.4.1.1.1" and similarly "4.4.1.2" to "4.4.1._1.2".
This is to ensure consistency within the Technical Specifications (see Surveillance Requirements of Technical Specification 3.4.1.2, numbered 4.4.1.2.1, 4.4.1.2.2 and 4.4.1.2.3 respectively). These are administrative changes.
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Page 3/4 4-2a - Adds " Amendment No. 38" to the bottom'of the page.
In j
Amendment No. 38, additions / modifications were made.to the decay heat removal Technical Specifications. These additions / modifications included
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adding page 3/4 4-2a and the Surveillance Requirements on that page.
However, this page was inadvertently issued without the reference to
.j Amendment No. 38.
Therefore. this is a typographical correction, i
Figure 3.4.2-a (page 3/4 4-4a) - Corrects the figure number; changes "3.4.2-a" to "3.4-2a".
This is to ensure consistency within the Technical j
Specifications. This is a typographical correction.
Figure 3.4.2-b (page 3/4 4-4b) - Corrects the figure number; changes "3.4.2-b" to "3.4-2b".
The, is to east.re consistency within the Technical Specifications. This is e typographical correction.
Page 3/4 4-5 Corrects the incomplete page number; changes "/4 4-5" to "3/4 4-5".
This is to ensure consistency within the Technical Specifica-tions. This is a typographical correction.
3.4.6.2 (page 3/4 4-15) - Changes " power operation" to " POWER OPERATION" in ACTION c.
In the Technical Specifications, defined terms appear in capitalized type; POWER OPERATION is a defined term. This is a typogra-phical correction.
4.4.6.2.1.c (page 3/4 4-16) - Corrects wording of Action Statement; changes
"... CONTROLLED LEAXAGE to the reactor coolant pump seals to..."
to 1
"... CONTROLLED LEAKAGE from the reactor coolant pump seals to...".
This is consistent with the definition of Controlled Leakage which is defined as being the leakage "from" the reactor coolant puup seals. This_is also consistent with Bases 3/4.4.6.2, Operational Leakage, which restricts operation with a total RCS leakage "from" all RC pump seals in excess of 10 GPM to the Controlled Leakage limit of 10 GPM. This is to ensure.the j
correct intent of the-Action.Statev nt.
Therefore,~this is a typo-graphical correction.
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Figure 3.4-1 (page 3/4 4-23) - Changes " Dose Equivalent I-131" to " DOSE EQUIVALENT I-131".
In the Technical Specifications, defined terms appear in capitalized type; DOSE EQUIVALENT I-131 is a defined term. This is a typographical correction.
j 3.4.11.c (page 3/4 4-32) - Corrects the valve number; changes "RC2" to "RC2A".
This is a typographical correction.
Page 3/4 5 Adds "(Continued)" to the top of the page. The Surveillance Requirements (4.5.2) start on page 5-3 and are continued onto page 5-4.
This is a typographical _ correction.
Docket No. 50-346 License No. NPF-3 Serial No. 1407 Att'chment 2 a
Page 7 Table 3.6-2 (page 3/4 6-20) - Corrects description of valve number SW1358, Penetration Number 10; changes " Containment Air Cooling Units SW Inlet Line" to " Containment Air Cooling Units SW Outlet Line".
Service water valve numbers SW1366, 1367 and 1368 are the inlet lines while SW 1356, 1357 and 1358 are the outlet lines. This is a typographical correction.
l Table 3.6-2 (page 3/4 6-20) - Corrects description of valve number DH77, Penetration Nueber 28; changes " Low Pressure trigection Line" to " Low Pressure Injection Line".
This is a typographical correction.
4.6.5.1. (page 3/4 6-29) - Deletes the two footnote references "**" and the footnote "** Eighteen month surveillance test due in March 1982 delayed until March 31, 1982" which has expired. These are administrative changes.
4.7.2.1 (page 3/4 7-13) - Corrects the' misspelled word; changes "coolnat" to " coolant". This is typographical correction.
4.9.12.1 (page 3/4 9-12).. Changes " Water Guage" to " water gauge". This typographical correction is to ensure consistency within the Technical.
Specifications.
Page 3/4 10 Changes (in two places) "startup" to'"STARTUP".
In the Technical Specifications, defined terms appear in capitalized type; STARTUP is a defined term.
These are typographical corrections.
3.11.2.1 (page 3/4 11-9) - Changes " RATE (s)" to " rate (s)" in ACTION a.
In the Technical Specifications, only defined terms appear in capitalized type; rate (s) is not a defined term. This is a typographical correction.
3.12.
~(page 3/4 12-1) - Corrects the Technical Specification reference in ACTION a; changes "6.9.1.11" to "6.9.1.10".
Technical Specification 6.9.1.11 is the Semiannual Radioactive Effluent Release Report,'not the desired Annual Radiological Environmental Operating Report as specified in 6.9.1.10.
Therefore, this is a typographical correction.
Page 3/4 12 Adds " ACTION:
(Continued)" to the top of the page. The ACTION statements of Technical Specification 3.12.1 start on page 3/4 12-1 and are continued onto page 3/4 12-2.
This is a typographical correction.
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3.12.1 (page 3/4 12-2) - Corrects the Technical Specification refercnce in ACTION d; changes "6.1.1.10" to "6.9.1.10".
Technical Specification.
6.9.1.10 is the desired Annual Radiological Environmental Operating Report.
There is no Technical Specification 6.1.1.10.
Therefore, this is a typo-graphical correction.
Page B 3/4 Q-lb - Corrects the page number;-changes "B 3/4 Q-1B" to "B 3/4 0-1b".
This is to ensure consistency within the Technical Specifications. This is a typographical correction.
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i Docket No. 50-346 License No..NPF-3 Serial No. 1407 Page 8 Page B 3/4 3 Corrects the misspelled word; changes " test" to " tests".
This is a typographical correction.
Page B 3/4 3-1.- Corrects the misspelled word; changes "THERMANL" to
" THERMAL". This is a typographical correction.
Bases 3/4.6.1.7 (page B 3/4 6-2) - Corrects the misspelled word; changes "occuring" to " occurring". This is a typographical correction.
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Bases 3/4.6.5.2 (page B 3/4 6-5) - Corrects the misspelled word; changes
" gage" to " gauge".
This is a typographical correction.
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Bases 3/4.7.8 (page B 3/4 7-6) - Corrects the misspelled heading; changes i
" CONTAMINATION" to " CONTAMINATION". This is a typographical correction.
j Bases 3/4 7.9 (page B 3/4 7-6) - Corrects the misspelled word; changes' i
"occuring" to '" occurring". This is a typographical correction.
5.6.1.1.a (page 5-5) - Corrects the misspelled word; changes "uborated" to "unborated". This is a typographical correction.
l SIGNIFICANT HAZARDS CONSIDERATION I
The proposed changes do not involve a significant hazards consideration because the operation of the Davis-Besse Nuclear Power Station, Unit No. 1, in accordance with these changes would not:
Involve a significant increase in the probability or consequences of an accident previously evaluated in the USAR because the accident conditions t
and assumptions are not affected by the proposed Technical' Specification and Bases changes.
The proposed changes do not involve a test or experiment, or a modification to a system. The proposed changes are administrative in
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nature and do not increase the probability or consequences of an accident previously evaluated (10CFR50.92(c)(1)).
Create the possibility of a new or different kind'of accident from any evaluated previously in the USAR because the accident conditions and assumptions are.not affected by the. proposed Technical Specification and i
Bases changes. The proposed. changes.do not involve a test or experiment, or a modification to a system and do not affect any' plant 'equipruent or oper-atienal procedures which could impact the probability.of an accident. The proposed changes are administrative in nature and involve no accident scenario. On matters related to nuclear safety, all accidents are bounded by previous' analysis and no new accidents are involved (10CFR50.92(c)(2)).
Involve a significant reduction in a margin of safety as defined in the basis for any Technical Specification because the amendment does.not affect any operating practices or limits nor any equipment or system important to safety. The proposed changes are administrative in nature and will not reduce the margin of safety (10CFR50.92(c)(3)).
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l l-Docket No. 50-346 License No. NPF-3 i
Serial No. 1407' Page 9 CONCLUSION i
Based on the above, Toledo Edison has determined that the Amendment request does not involve a significant hazards-consideration.
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