ML20212B285
| ML20212B285 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 10/24/1986 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20212B242 | List: |
| References | |
| P-87070, Q-3, NUDOCS 8703030513 | |
| Download: ML20212B285 (23) | |
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6 Issue 10 PUDllC FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 21 ;
) Service' PUBLIC SERVICE COMPANY OF COLORADO ATTAc t4 M GJl~ 2 TD P-8"7070 1
TITLE: DESIGN CONTROL SYSTEM y y / ~a i
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gv W a.4 c> Ichbsh E EC7;VE POPC k.,q;yed 5 C'Cf 14 Ge6 aeview me /o -;t <./- g t, j l TABLE OF CONTENTS Fi. ST.'.T.D l SECTION SUBJECT NON Cy ;7 p ag_D PAGE ccr/
l 1.0 PURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . y TU7. t.3._ . P. . .u '.T. l . . 3 rica tu u l 2.0 APPLICABILITY .. ........................................... 3 l 3.0 GENERAL REQUIREMENTS . ........... ......................... 3
.l 3.1 Definitions .................................... .... 3 l 3.2 Design Controls ........... ..... ................. .. 3 l 4.0 PROCEDURE .. . . ............... ....... ................. 4 1 4.1 Design Process General ........ .. ...... ............ 4 l 4.2 NED Responsibilities ............ ............ .... ... 5 l 4.3 Licensing Responsibilities ........ ............... .. 6 l 4.4 Nuclear Fuels Responsibilities ..... .................. 7 I 4.5 NPD Responsibilities ..... . .... . ............. . .. 7 l 4.6 Quality Assurance Responsibilities .. . ...... . . 7
[ 4.7 CN Processing ...... ..... ...... . ... . .... .. 8 l 4.8 CN Reissue Recuired .......... . ....... .. .. ... 9 l 4.9 CN Deviation Required .... ........ . . ............ 9 l 4.10 CN Installation Nonconformances . . . . .... .. 10 l ?.11 CN U;;date After Installation . . 10 8703030513 870220 t
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- Issue 10 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 21 SerVICG~ PUBUC SERVICE COMPANY OF COLORADO l 5.0 REFERENCE 00CUMENTS ........................................ 11 l 6.0 ATTACHMENTS ............................................... 11
! 6.1 Q-3A Change Notice Form .............................. 12 l '6.2 Q-38 Safety Evaluation Form .......................... 16 1 6.3 Q-3C Change Notice Reissue Form ...................... 17 l 6.4 Q-30 Environmental Evaluation Form ................. 21 l 7.0 CCMMITMENTS ............................................... 11
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$9fVICG'" Pusuc ssRVICE COMPANY OF COLORADO 1.0 PURPOSE To describe the engineering design controls employad for Plant modifications and changes to design documents.
2.0 APPLICABILITY This procedure applies to engineering design activities involving Plant or design documentation changes.
3.0 GENERAL REQUIREMENTS l 3.1 Definitions l 3.1.1 Enhanced Quality l That component for which the quality program l requirements have been identified, but which is rot l safety related. This includes non-safety related l fire protection (system 45 excluding safety related l portion), security system (excluding the gaitronix) l and components of packaging important to safety for l the transport of radioactive materials.
l 3.2 Design Controls l Design controls are required to assure that engineering de:ign activities performed for FSV Station modifications:
l 3.2.1 Include and correctly translate applicaole regulatory, FSAR and Technical Specification requirements.
l 3.2.2 Include and specify appropriate quality requirements including acceptance cri eria.
I 3.2.3 Soecify materials, parts, equipment and processes wnich have been selected and reviewed for suitability for intended applications.
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l l
FomM!C)272 22 3p3
0-3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION 4 f 21 service
- PUBUC SERVICE COMPANY OF COLORADO l 3.2.4 Are coordinated with all affected design interface groups.
I 3.2.5 Are processed in accordance with written procedures for review, approval, release, distribution and revision.
I 3.2.6 Are verified or checked for acequacy of design by performance of cesign reviews, alternate or simplified calculation methods or by the l performance of suitable testing for safety-related l and enhanced quality modifications only. If a test approach is employed in lieu of other methods, it l shall be conducted under the most adverse design condition in whicn the component will be expected I to function and shali be controlled to ensure that I the test results are representative and directly l support the design or design features.
l 3.2.7 "#* See Commitment 7.1."#* Are verified by qualified individuals other than the original designer (s) and other than the original designer's l Supervisor. (Safety-related and enhanced quality
[ modifications only).
l 3.2.8 Require the same processing and design controls as applied to the original design.
l 3.2.9 Are reviewed by the QA Division to verify appropriateness of quality provisions.
4.0 PROCEDURE 4.1 Design process General 4.1.1 Design work is performed within the Nuclear i Engineering Division in accordance with Procedure l ENG-1, or subcontracted and controlled per Procedures Q-4 and Q-7.
l FC AM aCl 372 22 Md3
0-3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION 5 f 21 SerVlC9"' PUBUC SERVICE COMPANY OF COLORADO 4.1.2 All modifications / changes are authorized and controlled by use of a Change Notice (CN) Form (Attachment Q-3A), which together with it's supporting documents comprises the authorization to enange the design of the Plant. The CN also authorizes changes to existing design documents or the creation of new design documents. CN's must be aoproved by NED, Licensing, Nuclear Fuels Group (if applicable), NPD, and QA prior to the performance of the work if they involve:
I a) Modifications to safety-related and enhanced l quality items or facilities, or b) Revisions to engineering design documents which alter design intent.
l Non-safety-related and non-enhanced quality modificacions for which engineering design, or material procurement is not required or requested, may be performed prior to CN initiation and approval, provided that plant management approval is obtained prior to performance of the work and that a properly approved CWP is used to accomplish the work. Under urgent situations as determined by the Shift Supervisor, or Superintendent of Operations work can proceed immediately and the CWP l can be issued as soon as possible. The department l responsible for the installation of l non-safety-related or non-enhanced quality modifications, requiring only plant management approvals, initiates a GSAR as descrioed by l Procedure G-3.
l 4.2 NED Resconsibilities l NED is responsible for ensuring that:
I 4.2.1 Each modi fication is analyzed to determine if any l portion is safety-related or enhanced quality. The l design engineers shall identify the applicable l design input requirements including regulatory l requirements, quality requirements, codes, l standards, specifications, qualification t
l considerations, seismic, fire protection, security, l
l environmental, and long term program considerations l .such as the EQ program.
i 1
FoRMtCl372 2:.3sa3
f.;-3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION 6 f 21
$9fVlCe* PUBLIC SERVICE COMPANY OF COLORADO 1 4.2.2 *#* See Commitment 7.1 *** Design outputs for l safety-related and enheaced quality modifications are subjected to a design verification process
- erformed by cualified individuals other than the original cesigner and other than the original designer's supervisor, s
l 4.2.3 The CN packages detail design activities and
- document the results of technical evaluations by Engineering to justify the safety and correctness of the modification, j ,
l 4.2.4 Appropriate test requirements are provided .(here required to prove or veri fy the CN design or function.
l 4.2.5 All controlled design documents affected by a CN are identified in the CN package anc that configuration of the affected documents controlled by the NED are identified.
I 4.2.6 Deviations from approved CN's/CWP's are documented, controlled and approved by Engineering and Quality Assurance on CWP Deviation Report Forms as described by Section 4.9.
l 4.2.7 CN changes are documented and controlled using Change Notice Reissue Forms (Attaches:.nt Q-3C). 4 l 4.2.8 NED will conduct as-built vertfication of installations and as the resulttof a final design review, cetermine additional document update requirements, if any, and toitiate CN close-out. -
l 4.3 Licensing Resconsibilities l Licensing is responsible for ensuring that:
l 4.3.1 A safety evaluation of each CN is performed to determine whether the proposed modification may be an Unreviewed Safety Question. The safety evaluation is documented on tne Safety Evaluation Form (Attachment 0-38).
I 4.3.2 An environmental rivaluation of each CN is performed to determine whether the proposed tredification tray be an Unreviewed Environmental Question. The environmental evaluaticn is documented on che Environmental Evaluation Form ( Attacnment Q-30).
FoRWCJ 372 22 3643
Q-3 Pub'lic FORT ST. VRAIN NUCLEAR GENERATING STATION f 21
-SGTVICG~ PUBUC SERVICE COMPANY OF COLORADO l.M 4.3.3 Safety-related and enhanced quality CN's and those identified as having a potential for significant ,
nc; radiological effects on the general environment 2 are presented to PORC to determine if the change is safety significant or involves an Unreviewed Safety
.c Question or an Unreviewed Environmental Question.
3 ,
. l 4.3.4 CN's determined to be Safety Significant, or
, involving an Unreviewed Safety Question or
/ Unreviewed Environmental Question are presented by the Manager, Nuclear production to the NFSC for review and verification of whether or not the CN involves an Unreviewed Safety Question or an Unreviewed Environmental Question.
l 4.3.5 CN's involving an Unreviewed Safety Question or an Unreviewed Environmental Question are submitted by Nuclear Licensing to the NRC for concurrence prior
! to implemantation.
- I 4.3.A CN's affecting reactor core consumables (see l section 4.4, p re rputed to Nuclear Fuels for I review.
l 4.4 uclear Fuels Reso3ns gilibjes l NuclearFuelsisrespons,h';forensuringthat:
l 4.4.1 The performance of core consumables such as; l nuclear fuel, reflector blocks, control rod worth,
, i neutron sources, burnable poisons and the reserve l shutdown sys_ tem are not degraced as a result of the l modification, l l 4.5 gelear production Res::ensibilities
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1 Nuclear Production is responsible for ensuring that:
l 4.5.1 The general affect of the modification on plant operations is evaluated for changes to the i~
l Technical Specifications, plant operating l procedures, maintenance procedures, radiological l procedures, and training procedures.
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0-3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION 8 f 21 SerVlCe* Pusuc senviCE COMPANY OF COLORADO l 4.6 Quality Assurance Resconsibilities l Quality Assurance is responsible for ensuring that:
l 4.6.1 The design inputs for the modification reflect the l aoplicable codes, standards, specifications, l . regulations and programs (i.e., EQ program) and
! that they are properly addressed in the design l analysis section of the enange notice.
l 4.6.2 The material is specified, crocured, stored, and l documentation requirements are in accordance with l approved procedures.
l 4.6.3 The installation instructions are complete and l detailed enough to provida adequate information to l the field for construction.
i 4.6.4 Testing and inspection requirements are specified l and appropriate for the work ceing performed.
i 4.6.5 The appropriate documents are updated to reflect l the modifications, additions, or deletions as a l 'l result of the change notice.
l l 4.7 CN processing l 4.7.1 Upon receipt of author,ization to proceed with the CN and detail design, the CN is processed as
[ described by procedure ENG-1.
l 4.7.2 Required control of CN processing is assured by assignment of a CN, coordinator to follow the progress of each CN in accordance with ENG procedures.
l 4.7.3 On completion of dasign activities and interface verifications the CN is forwarded to Nuclear Licensing.
l 4.7.4 Nuclear Licensing reviews the CN, performs i licensing evaluations, and sends it to Nuclear
) Fuels if applicable, or, returns the CN to NED.
l 4.7.5 NED acproves the CN and forwards it to Technical Services.
l 4.7.6 Technical Services reviews and obtains NPD approval and forwards CN to NED-Site.
FORM sC3 372 22 W
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Public FORT ST. VRAIN NUCLEAR GENERATING STATION e9 f 21 service
determines distribution requirements ano forwards CN to QA.
l 4.7.8 The QA Services Manager or his designee reviews / approves the CN and forwards CN to Design Document Clerk - Site for distribution.
I 4.7.9 The Design Documenc Clerk - Site reproduces ano distributes the CN as required by the Distribution Handbook.
l 4.5 CN Reissue Raouired l 4.8.1 Changes in the design or installation requirements that exceed the limitations for CWP-DR requests as l defined by paragraph 4.9, and which are required before further work can proceed, may be processed utilizing an Action Request (AR) for CN reissue.
(See Procedure G-3).
l 4.8.2 On receipt of the AR, (if applicable), NED initiates the CN reissue as described by ENG-1.
l 4.8.3 The NED approved CN reissue is processed as l described by paragraphs 4.7.3 through 4.7.9.
l 4.9 CN Deviation Recuired If during CN implementation, it is determined that a deviation from the design or installation instructions is required, a deviation request may be processed in accordance with G-9 using a CWp-OR provided that:
l 4.9.1 The materials and components as specified in the CN are not compromised. Materials and components may be substituted if the substitutions meet or exceed the requirements set forth in the CN.
l 4.9.2 The design intent, process flows, and/or the safety and environmental evaluations as specified in the CN is not altered.
l 4.9.3 The environmental qualification (as defined in l 10CFR50.49) and seismic qualification of the item l has not been affected.
FoRVIC)372..*2 3H3
1 0-3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION '
f 21 SerVICG"" Pusuc sanviCE COMPANY OF COLORADO l l 4.9.4 The following applicable precautions are not compromised:
a) The eff~e cts of the activity on nearby equipment, structures, materials, components, cabling or pioing with particular emohasis on the safety-related aspects of these items has been identified.
b) Critical pieces of equipment have been identified.
c) The work has been planned to avoid damage to nearby plant equipment.
d) The use of combustible materials is avoided or closely controlled in accordance with the requirements of Procedure P-8.
e) Precautions, to avoid damage to adjacent areas by welding or other hazardous operations have been taken in accordance with the requirements of Procedure P-8.
f) The integrity of cable fire stops, seals, and wall penetrations have been maintained and that measures have been established to ensure they are returned to their original design intent.
i l
g) Adequate ventilation has been ensured.
1 4.9.5 An independent design verification is performed in accordance with G-9, for all DR's written which l involve safety-related or enhanced quality equipment or components. The IOV will be performed before the plant system being modified can be returned to service.
l l l 4.10 CN Installation Nonconformances If on inspection of a CN installation, departure (s) from specified requirements are encountered, a Nonconformance Report (NCR) is initiated by QC and processed as described by Procedure Q-15. Nonconformances associated with site-specific contractor work may be initiated and processed in accordance with a previously approved Contractor Project Manual as orovided for by l Procedure Q-2.
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Q-3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION l f 21 SerVICO' PUBUC SERVICE COMPANY OF COLORADO l 4.11 CN Uodate After Installation l 4.11.1 On task completion, a listing of any AR's di,'isticns, or "CR's dispcsiticnad "oss-as-is" cr
" repair", is forwarded to NED by QA/QC.
l 4.11.2 NED reviews the AR's, deviations and NCR's and l determines the need for CN reissues.
5.0 REFERENCE DOCUMENTS 5.1 F5AR -
Appendix 3, " Quality Assurance Program for Plant Operation" l 5.2 Procedure ENG-1, " Control of Modifications and l Occumentation Changes" l 5.3 Regulatory Guide No. 1.64, " Quality Assurance Requirements l for the Design of Nuclear Power Plants" l i.4 APM Q-2, " Quality Assurance Program" l 5.5 APM Q-4, " Procurement System" l 5.6 APM Q-7, " Control of Procured Materials, Equipment and Services' l 5.7 APM Q-15," Control of Nonconforming Items" l 5.8 APM G-3, " Action Request - Preparation and Processing" l 5.9 APM G-9, " Controlled Work Procedures" l 5.10 APM P-8, " Fire Fighting and Prevention" 6.0 ATTACHMENTS I 6.1 0-3A Change Notice Form l 6.2 Q-38 Safety Evaluation Form l 6.3 Q-3C Change Notice Reissue Form l 6.4 0-30 Environmental Evaluation Form 7.0 CC.vMITMENTS The step ( s) and section(s) listed below may not be deleted without issuance of comparable controls. The procedure itself, if initiated as a result of commitment corrective action, may not be deleted without issuance of comparable controls.
l 7.1 Steps 3.2.7 and 4.2.2 are the result of corrective actions mace in response to CAR 35-060.
l l
Q-3 Attach Q-3A Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 50 SerVICO* PUBUC SERVICE COMPANY OF COLORADO Page 12 of 21 ON. NO
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FCmMiC)372 22 3643
o 0-3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION 3 {0 service
- PUBUC SERVICE COMPANY OF COLORADO Page 13 of 21 SAFETY EVALUATION FORM INSTRUCTIONS The numbers below correspond to those in the sample Safety Evaluation Form shown on Page 4 of this attachment.
RESPONSIBILITY ACTION INITIATOR 1. Circles initials that identify document being evaluated.
- 2. Enters number of the appropriate document. Obtain numbers for:
- a. CN's from NED Computer Technician
- b. TCR's from Shift Supervisor
- c. SCR's from Nuclear Documents Specialist
- d. PC's from QA Computer Specialist
- f. OTHER as required
- 3. Enter page number that the Safety Evaluation will appear in the document package.
- 4. Identify with an "X" each type that applies to the change.
- 5. Indicate "YES" and "NO" for each classification listed. Criteria for each is identified below:
- a. Class I -
Specification SR-6-2 (Safety Related Component List) and FSAR Table 1.4-1.
- b. Safe Shutdown - Specification SR-6-2 (Safety Related Component List) and FSAR Table 1.4-2.
- c. Safety Related - FSV Administrative Procedure Attachment G-1A.
- d. Engineered Safeguard - FSAR Section 6.
- e. Plant Protective System -
FSAR Section 7.1 and the following drawings: E, E-1203, IB, IC anc P&I.
FCRM tCl 372 3 3643
' Q-3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION f33u {0 service"* PU8UC SERVICE COMPANY OF COLORADO Page 14 of 21 RESPONSIBILITY ACTION
- f. Security System -
Security Plan and/or Security Drawings.
INITIATCR 6. A review must be done for all sections of the FSAR and/or Technical " Specifications that may relate to the change or test in progress. All sections reviewed that were found to be applicable shall be listed together with a statement summarizing the results of the review.
(Refer to STAIRS Licensing Data Base for FSAR and Tech Spec Review as described in the Nuclear Records Management Manual).
NOTE': Identify sections reviewed .for both the FSAR and Tech Specs.
- 7. The effect of the change or test upon the FSAR and the Technical Specifications must be considered. This requires that a review be made of all relevant sections of these documents for possible impact.
If it is determined that the proposed change or test does have an impact on the FSAR or Technical Specifications, and that the impact is sufficient to justify making changes to these documents, then the affected sections of these documents shall be listed. Suggested revisions, deletions or additions shall be initiated per FSV Administrative Procedure G-2.
t NOTE: Accress both the FSAR and Tech l Spec.
l 8., 9., & 10. As described in 10CFR50.59, these questions are used to identify an unreviewed safety question. Answer each question and provide a clear, concise
[ basis for each.
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s Q-3 Public h Q-38 FORT ST. VRAIN NUCLEAR GENERATING STATION g SerylC9' PUBLIC SERVICE COMPANY OF COLORADO Page 15 of 21 RESPONSIBILITY ACTION INITIATOR 11. If section 3(A), 3(B) g 3(C) is checked "YES", answer this question "YES"; if not, answer this question "NO".
- 12. Answer this question based on the definition of " Safety Significant Change" given in FSV Administrative Procedure, G-1.
- 13. Upon completion of Action 11 and 12, enter signature and date.
APPROVING 14. Sign'and date approval.
SUPERVISOR PomMiC:372 22 3643
0-3 Attach Q-38 FORT ST. VRAIN NUCLEAR GENERATING STATION Issuei0 0Public SerVICO"' PUBLIC SERVICE COMPANY OF COLORADO Page 16 of 21 PubilC 'on s- 4 a s u. 4 cENeaAriNo srAries
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Q-3 4 Attach. Q-3C Public FORT ST. VRAIN NUCLEAR GENERATING STATION IS$ue 10 SerVlCG~ PUBLIC SERVICE COMPANY OF COLORADO Page 17 of 21 FCRT ST. VRA.N NLCLEAR GENERADNG STADCN CN Public PUSUC SERVICE COMPANY OF COLORADO BY Service' p,c, CHANGE NOTICE REISSUE J'C8/ ACCT #
SYSTEM NO. RCSSUE a SU8 JECT OF CRIGiNAL CN CISCRIPDCN OF REISSUE m!S CN REISSUE INVOLVES:
YES NO 1 C C Change to the oefety evaluation (Attach effectwo safety eveauanoni 2 C C Change to tne envror montes evaluanon (Atteen effectwo envronmental evaluscon) 3 C C Change in the safety reisted c'aeerficanon a C C Change in deogn etent
! C C Change in scope l 6 C C change e instenacon / procurement resoonsetsiioes ,
7 C C Change to the instadacon / procurement pacmage '
! $ 2 C Change to the deogn bacxground eformanon package l 7 C C Change to the document uooste pacmage to C C Change nonce :ancenlacon f
ATTACHMENTS.
- CHANGE NOTICE REISSUE COCRO!NADON SHEET
- EFFECT:VE DATE SAFETY EVALLADQN: CVERALL EFFECDVE DATE ENVIRONMENTAL EVALUADON: OVERALL EFFECTIVE QATE l
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l AEVIEWS, APPROVALS:
NUCLEAR LNGINEERING , , , , , , , , , , ,
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A t Q-3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION
{0 SOfVICe* PUBUC SERVICE COMPANY OF COLORADO Page 18 of 21 ENVIRONMENTAL EVALUATION FORM INSTRUCTIONS Each change in plant design or operation or performance of tests or experiments, shall be reviewed to determine whether or not the activity has the potential to be an unreviewed environmental question. All changes in plant design are reviewed to determine whether or not they have the potential for causing environmental impact, except the following:
- 1. Changes in plant design or operation or performance of tests or experiments which do not affect the environment are not subject to this in depth evaluation.
- 2. Changes in plant design or operation and performance of tests or experiments which are required to achieve compliance with other Federal, State, or local environmental regulations are not subject to an Environmental Evaluation.
- 3. Activities are excluded from this evaluation if all measurable nonradiological effects are confined to the on-site areas previously disturbed during site preparation, plant construction and previous plant operation.
Those modifications identified as having potential environmental impact are then reviewed in depth to determine whether or not they constitute an unreviewed environmental question.
Before engaging in construction o'r operational activities which may affect the environment, an Environmental Evaluation form shall be completed.
If the Environmental Evaluation, as well as the PORC and NFSC, concludes that the activity involves an unreviewed environmental question, than the construction or change is not allowed until NRC approval is obtained.
A proposed change, test or exoeriment shall be deemed to involve an unreviewed environmental question if it concerns (1) a matter which may result in a significant increase in any adverse environmental impact previously evaluated in the Final Environmental Statement (FES) as modified by NRC's staf f's testimony to the Atomic Safety i Licensing Board, supplements to the FES, environmental impact appraisals, or in any decisions of the Atomic Safety and Licansing Board; or (2) a significant change in effluents or power level (in accordance with 10CFR Part 51.5(b)(2)); or (3) a matter not l previously reviewed and evaluated in the documents specified in (1) above, which may have a significant adverse environmental impact.
l l
t FomMIC)372 22 3643
4
, 0-3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION u 10 0 service
- Pusuc SERVICE COMPANY OF COLORADO Page 19 of 21 The numbers below correspond to those in the sample Environmental Evaluation form shown on Page 4 of this attachment.
RESPONSIBILITY ACTION INITIATOR 1. Identify type of document being evaluated.
- 2. Enters number of the appropriate document.
- 3. Enters page number that the Environmental Evaluation will be given in the document package.
- 4. Identify type of evaluation being prepared.
S. Identify each applicable response to these two questions. If either answer is YES, sign and date form (item 9). If both answers are NO, the remainder of the form shall be completed.
- 6. For those activities determined to h' ave potential environmental impact, further evaluation is required to assess whether or not they constitute an unreviewed environmental question. A review shall be done for all sections of the Final Environmental Statement (FES) that may relate to the change in progress. Additionally, any associated supplementary environmental cocuments such as described in page one of Attachment Q-30 will also be reviewed. All sections and documents reviewed shall be listed together with a statement summarizing the results of the review.
- 7. The effect of the change upon the FES must be considered. Items 7A.
78 and 7C must be answerec including a clear statement indicating the basis or justification for the answer.
FoAMIC1372 *2 3H3
. Q-3 A Public FORT ST. VRAIN NUCLEAR GENERATING STATION su 50 YO7 Service ~ pusuc sanvice company or coton4oo Page 20 of 21
- 8. Any "YES" answer to itens 7A, 78 or 7C requires a "YES" answer to this question, otherwise, a "NO" entry is appropriate.
- 9. Sign and date form.
APPROVING SUPERVISOR 10. Sign and date approval.
FoAMiCIT72 22 3843
i s
o 0-3 Attach Q-30 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 50 0 service
- PUBUC SERVICE COMPANY OF COLORADO Page 21 Of 21 Public 'en sr oAis wCtEAR menAm s AncN
$grylC9e PUBUC SERVICE COMPANY OF COLORADO CN / OTHER ENVIRONMENTAL EVALUATION NQ.
PAGE CATEGOAV TYPE. C CN Overed C CN Submittal Otner Are as measuracle nonradiciose.ai e*ects of mis actnney conMeed to the on ste areas crev.ousry deturned cunng site propersoon, cient construccon or previous piant coersoon? C yes C No State mass is me actnnty recuwed to acti eve comonence wim Feeeral $ tate or locas envwonenentad regulacons? O Yes C No Aconcable Reguianons wrt it e,,, =,w.e w e _ __ _ . __ n. se ow see = amme er ese an s ao w
= mew,an m . v.a.mi newv rorme aes in== e-. - _ anni a can=== e ==wer er me em.saea w I.
is tre actnneyidenoNdin me Mnal en. e - e. tad sts ement (FES) C Yes C No or $wooiementary Envwonmented occuments (See Q 3)?
Iconefy documents and document sectons reviewed
- 2. Cetem='ne whetre or not tne octnney evo#wed is an unreviewed environmeatsa ovestion unng the followeg guicennes (if tre er raer to any of tre fainowing quesocns :s Yai, tnen snes actniity evenies an unroviewed e9vwommeetas queston.)
(Al was thrs actn itv reeutt in a s.gnincant increase a any soverse env'ronmental irnpact previounty eveausted in 'ae FES? C Yes C No State ease I
IB) Will tras actnnty reeust a e significant enange 'n me types. or a signiMeant increase in tre armounts of ediusats. or a signiacant increcee in me authented power ieve? O Yes C No State beme ICI Coos ems acovrty involve an envwontnentat matter not previousv reviewed and eveauated in tre FES?
! C Yes C 'do State name Oces the actnrity invorwe an unreviewed e*vventesetas cuestion? O Yes 2 No
. I 3v Accreved l e.ea r..e ., . .w.*s as -s
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- CAMICl372 22 3643
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FORT ST. VRAIN NUCLEAR GENERATING STATION
& Public NO. k! J ~ f b f f W Service = PUBUC SERVICE COMPANY OF COLORADO PROCEDURE DEVIATION REPORT PAGE OF PROCEDURE NO. TIT E , .
. ISSUE NO.
&-3 \ es\64 bxw. Sq.5 csx lO IS PORC REVIEW REQUIRE 0P kvES ONO --
.ttQI.E. IF PORC IS REQUl6ED. THE INmATOR IS RESPONSIBLE TO ENSURE THAT THE POR IS SU8MITTED FOR PORC REVIEW NO LATER THAN 14 DAYS FROM THE POR IMPLEMENTATION DATE.
A .NO . CH NGEO FROM CHANGED TO REASON FCR CHANGE
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tREQUIREO IF AFFECTED STEPISI REQUIRE QC OR INVOLVE TESTING OR MAINTENANCE ON SAFETY RELATED EQUIPMENT)
I TEM ORARY PERMANENT.DCCF ATTACHED CEVIATION CAT G{RY:
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EDRC 7 0 4 DEC 161986 PORC. , , ,, , , g, INITIATOR . FORWARD CRIGINAL TO PORC CLERK. ATTACH COPY TO PROCEDURE BEING DEVIATED Fv+ti 372 30 33tl a *w as aae e e ea e . .a r s e . eae t c . e .- _ _ _ _
s Cn.NO. ,
F RT ST. VRAIN NUCLEAR GENERAMG SWlON
. Public PAGE DATE
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Service ~ PUBLIC SERVICE COMPANY OF COLORADO y
ro,,,acman. CHANGE NOTICE JO # / ACCT. #
DESCRIPTION DESCRIPTION:
CN GENERATED IN RESPONSE TO (COMMITMENT JOB NO., DCAR, i Et E BULLETIN, ETC.):
SYST. NO:
EQUIP, NO:
SPEC. NO:
SAFETY EVALUATION: SEE DETAILED SAFETY EVALUATION O SAFETY RELATED C NONSAFETY RELATED C MODIFICATION O DOCUMENT CHANGE ONLY REMARTS PAGE SCHEDULE (NumEner CN Cover Pages Sequentially: 1, 2, 3, etc.)
APPROVA 1
l NUCLEAR ENGINEERING , , ,
P OD.
i s.c.=4 rva si ioa r si i s..>.a rva e, , oa r e, PORC REVIEW: REQUIRED IF CHANGE ls SAFETY RELATED OR HAS POTENTIAL FOR CRE.ATING AN UNREVIEWED ENVIRONMENTAL CUESTION.
YES NO C C SAFETY SIGNIFICANT C C UNREVIEWED SAFETY QUESTION C C UNREVIEWED ENVIRONMENTAL QUESTION . ..ma r . .ura o. oa rs.
NFSC REVIEW: REQUIRED ONLY IF PORC DETERMINES CHANGE TO BE EITHER SAFETY SIGNIFICANT, AN UNREVIEWED S AFETY CUESTION OR t
AN UNREVIEWED ENVIRONMENTAL QUESTION.
YES NO O O UNREVIEWED SAFETY QUESTION C C UNREVIEWED ENVIRONMENTAL QUESTION , , , , , , , , . ,y ,a , a a r si i
NRC REVIEW:
- REOUIRED ONLY IF NFSC CONCURS THAT THE CHANGE IS AN UNREVIEWED SAFETY QUESTION OR ANUNREVIEWED ENVIRONMENTAL QUESTION.
NRC REVIEW COMPLETED ,,,,,, ,, , 3 7,3 ,,,,,..,,c,
' NRC REVIEW REQUIRED PRIOR TO IMPLEMENTATION CLOSE OUT (To De Comssloted By NE
- DOCUMENT REVISION COMPLETED 37,3 CHANGE NOTICE CANCELLED .p r ui
, ma rusivi l
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