ML20128F255

Forwards Identification of Amend 3 Changes to Updated Fsar. Amend Includes Changes to Procedures,All Safety Evaluations Re License Amends & All Analyses of New Safety Issues

ML20128F255
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	07/01/1985
From:	Withers B PORTLAND GENERAL ELECTRIC CO.
To:	Butcher E Office of Nuclear Reactor Regulation
References
NUDOCS 8507080186
Download: ML20128F255 (8)

Text

%

e em -

-ame Blrt D Waus Vce Presdort July 1, 1985 Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation ATTN: Mr. E. J. Butcher, Acting Chief Operating Reactors Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington DC 20555

Dear Sir:

TROJAN NUCLEAR PLANT Updated Final Safety Analysis Report. Amendment 3 In accordance with 10 CFR 50.71(e), one original and 12 conformed copies of this letter and its attachments are submitted in support of Amendment 3 to the Trojan Nuclear Plant Updated Final Safety Analysis Report (FSAR), 13 sets of which have been transmitted under separate cover. This amendment includes the effects of: (a) all changes made in the facility or proco-dures as described in the Updated FSAR submitted on July 20, 1982 and revised by Amendments 1 and 2; (b) all safety evaluations performed by PGE, either in support of requested license amendments or in support of conclu-sions that changes did not involve an unreviewed safety question; and (c) all analyses of new safety issues performed by or on behalf of PCE at NRC request. Administrative and editorial changes have been included, as well as technical corrections and clarifications.

The Updated FSAR is organized consistently with the format of the Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, NUREG-0800 (July 1981). Each copy of Amendment 3 is accompanied by a set of instructions for inserting it into the Updated FSAR. The replace-ment pages contain " change bars", ie, vertical lines in the margin adjacent to the portion actually changed, and each replacement page is labeled

" Amendment 3 (July 1985)".

8507000186 850 44 ADOCK 0500 PDR pDR hOi ,

121 S W Sa mon Owt Fartard Oregon 97204

W M M C Ofi4 X MTf tie. E. J. Butcher July 1, 1985 Page 2 The attachment identifies the changes due to analyses submitted to the Comission or prepared pursuant. to Commission requirements and the changes made under the provisions of 10 CFR 50.59. Other major sources of amendment information are also identified.

Sincerely,

_ d Bart D. Withers Vice President Nuclear Attachments c: Mr. Lynn Frank, Director State of Oregon Department of Energy Mr. John B. Martin Regional Administrator U.S. Nuclear Regulatory Commission Region V Subscribed and sworn to before me this let day of July 1985.

l I

M le Notary Public of ffregon OMyCommissio e b -

Trojan Nuclear Plant Mr. E. J. Butcher Docket 50-344 July 1, 1985 License NPF-1 Page 1 of 6 UPDATED FINAL SAFETY ANALYSIS REPORT IDENTIFICATION OF AMENDMENT 3 CHANGES A. Plant Design Changes - Federal regulations (10 CFR 50.59) and the Trojan Facility Operating License NPF-1 allow changes to be made to the facility as described in the safety analysis report, and tests or experiments to be conducted which are not described in the safety analysis report, without prior Nuclear Regulatory Commission (NRC) approval, unless the proposed change, test, or experiment involves a change in the Technical Specifications incorporated in the license or an unreviewed safety question. The following Plant Design Changes were evaluated, and it was determined that they did not: (a) increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety, as previously evaluated in the Final Safety Analysis Report (FSAR); (b) create the possibil-ity of an accident or malfunction of equipment important to safety, as previously evaluated in the FSAR; or (c) reduce the margin of safety as defined in the basis for any Trojan Technical Specifications.

1. Plant Design Change 76-112 modified the main turbine control system to run the main turbine back to 70-percent load following the loss of one main feedwater pump. Section 10.2.2 was revised to describe this modification.

2. Plant Design Change 81-045 installed redundant sulfur dioxide detectors in the Control Room Ventilation System. Sec-tions 2.2.3, 6.4.4, and 9.4.1 were revised to describe these l detectors. l

3. Plant Design Change 75-196 transferred power for the Plant computer to a transformer from unregulated Bus B26. Sec-tion 8.3.1.1.5.1 was changed to delete the description of powering the computer from an inverter.

4. Plant Design Change 81-051 provided a flow sensor for monitoring the recirculation flow rate of the makeup water system neutralis-ing tank. Figure 9.2-8 has been revised to show this change.

5. Plant Design Change 82-002 replaced the water cooled chiller in i the condensate domineralizer sampling system with an air-cooled t chiller. The new chiller is shown in Figure 9.3-4.

6. Plant Design Change 82-006 added pressure switches to the inlet l of each condensate domineralizer. Revised Figures 10.4-13 and 10.4-14 show this change.

i

I Trojan Nuclear Plant Mr. E. J. Butcher Docket 50-344 July 1, 1985 License NPF-1 Page 2 of 6 B. Licensing Document Change Requests (LDCRs) - Licensing documents con-sist of various PGE Topical Reports and the Trojan Updated FSAR.

Under 10 CFR 50.59, changes are permitted to these documents if a change to the Operating License or Technical Specifications does not result and an unreviewed safety question is not created. The follow-ing LDCRs were evaluated, and it was determined that their changes do not involve a change to the Operating License. Technical Specifica-tions, or an unreviewed safety or environmental question.

1. LDCR 84-16 was prepared to clarify the main steam PORV setpoints.

Section 10.3.2 was changed to include this clarification.

2. LDCR 84-17 amended PGE-1028, " Regulatory Guide Policy Manual".

Sections 3.1 and 15.7 were revised to clarify conformance with Regulatory Guide 1.25. Sections 7.6.2.7 and 8.3.1.4 were changed to describe electrical separation (Regulatory Guide 1.75) associ-ated with the Reactor Vessel Head Vent System.

3. LDCRs 84-18 and 84-23 revised PCE-1021. "Offsite Dose Calculation Manual". Chapter 11 was revised accordingly.

4. LDCR 84-13 condensed the description of review and audit. Sec-tion 13.4 was changed to Reference PGE-P010 and appropriate procedures.

C. License Amendments - License amendments to the Trojan operating License and Technical Specifications are approved by the NRC. Many of these amendments affect the Updated FSAR. Information from the j

following license amendments is included in Amendment 3 to the i Updated FSAR.

i

1. Operating License Amendment 92 (License Change Application 103) made several changes to upgrade fire protection requirements and administrative controls. Section 13.4 was revised to incorporate these changes.

2. Operating License Amendment 96 (License Change Application 108) modified the remote shutdown instrumentation. Section 7.4.1.1 was changed to address this modification.

3. Operating License Amendment 99 (License Change Application 50) authorized numerous changes to the Radiological Effluent Techni-cal Specifications (RET 3). Chapter 11 was revised to be con-sistent with the RETS.

4. Operating License Amendment 98 (License Change Application 98) authorized reduction of the boron concentration in the boron injection tank. Chapters 6 and 15 were revised to describe this I change.

Trojan Nuclear Plant Mr. E. J. Butcher Docket 50-344 July 1, 1985 License NPF-1 Page 3 of 6

5. Chapter 13 was revised to reflect organizational changes. These changes are based on License Change Application 119, dated April 4, 1985.

D. PCE to NRC Correspondence - This correspondence includes analtses and information submitted to the NRC or prepared per NRC requirer ents.

The following correspondence affects the FSAR and was incorr'cated in Amendment 3:

PGE (B. D. Withers) to NRC (D. G. Eisenhut) letter dated July 6, 1984 regarding response to Generic Letter 84-14. As a result of this lette", Section 13.2 was revised.

E. Internal PGE memorandums, NSSS vendor and AE correspondence, and correction of errors discovered in everyday use of the Updated FSAR have resulted in revisions and editorial changes, including the following:

Expands Section 3.1.4 to describe the alternate ultimate heat sink for consistency with Technical Specification 3/4.7.5.

Revises Section 2.2.3.2.1 to correctly describe chlorine cylinder valves, i

f Changes the reference citation in Table 2.1-1 and Section 2.6 to l PGE-1021.

l Adds a discussion of the 1980 census to Section 2.1.3.1.

Expands the description of meteorological instrumentation in Section 2.3.3.2.1.1.

Revises Figure 4.3-35 to show rod cluster control assembly pattern.

Describes modifications in Sections 3.9, 4.4, 4.5, and 15.6 to reactor internals which reversed the flow direction in the core barrel / baffle region.

j Revises Table 5.1-1 to correct the Reactor Coolant System volume and make it consistent with Technical Specification 5.4.2.

Revises the RCS chemistry specifications in Table 5.2-5 to conform with Technical Specification 3.4.7.

Expands the list of ESF equipment in Section 6.0.

Clarifles the description in Section 6.2.5.5 of hydrogen analyzers and associated sampling.

4 3

d Troj$i 8Fuclear Plant '

, Mr. E. J. Butcher Doclet 50-344\- i '

[":

July 1, 1985 License ifPF-1 .

T. 1

, , Page 4 of 6 e t, .

• Clarifies Dae descriptiob of the' Reactor Vessel Head Vent System

.V in' Sections'7.6.1.7 and 7.6.2.7.

u 9 1

Reviser.thedescriptit.nof!keactorConlantSystemwide-range pressurelin Table 7.5-$ rto 'itidicate that only one channel is r'ecorded. ,[

\[3 .9 %'

Changes Section 7.21.2.1sto cl'arif[the availability of the 3

j power range hif .h po.481va, heutiron flux rate trip.

J

.5 , Revises Table 7.2-4sto clarify references to the Technical

.Specifiedtions. ,

-u i _

s Revises'Sectic,n 7.6.1*.5 to clarify the description of the jahblocCPSZRReliefValvesCircuitry" alarm.

-x

• L. s i A

., .) g Makes miscellaneo^Nus changed to Tables 7.5-1 and 7.5-2 to

, coirectly de<icri'ce' the main control bocrd indicators and to be

, J ;, 4

" mofe consG ' "* tent witVjdevised Section~7.4.1.1.

4

( 1 g~ 6;.

g Clarifies the setsmid design of the subcooling margin monitors

't rg in Section 7.9.2.4

• 4:. '

I.

. 3. , ; >

. s

( Deletes referer.jsgia Section 9.5.4.3 to maintaining a complete J , spare diesel transfer pump asrambly.

', [.

_, Deletes description in Section 9.5.4.4 of the method used to lf~,

N. determin6;iC sater exists in diesel fuel oil storage tanks.

-o ,  !

,,~ Changesr'atingIfheate'rdbainpumpsto1000hpinTable10.4-2.

( ', ' s . a, j

i N "

Clarifies the tases and analysis for the cooling tower and basin '

q as the ultimate heet; sink in Sections 9.2.1.3 and 9.2.5.2.

t 4

, , Revises Table 9.2-4 to correctly indicate the service water 4 3 strciners mesh opening sire.,

f

'i , i  % i

' Revises Section 9.7.3 to correctly des.cribe the Makeup Water Treatment System. =

g s Adds new Section 9.1.5 on overhead Heavy Load Handling Systems.

t .

$, 'Slarifles.tho' discussion of heavy load movement in Sec-

',. i tion 9.1.4.'2 d.1.

' g

] ' "

4

, v.

(. ' Y.

,e :'- 4.

, ,, o q

.(

q' )

currecfaitha AEM setroint fog '

isolation of the control room in Se exion" 7.'4.}.2.1. '

h)j y 4 A * \;

j k A D n c 1

[

m

) 1, 9

J _ p ej,O Q,Q .

'y

s Trojan Nuclear Plant Mr. E. J. Butcher Docket 50-344 July 1, 1985 License NPF-1 Page 5 of 6 Adds a monthly sampling requirement for sulfates in the spent fuel pool to Table 9.1-2 and adds a limit of 0.15 ppm for sulfates in the spent fuel pool to Table 9.1-1.

Adds a ocacription of the Post-Accident Sampling System for reactor coolant and Containment atmosphere to Section 9.3.2.

Adds a discussion of degassing the Reactor Coolant System through the pressurizer sample lines to Section 9.3.2.2.1.

Adds a description of the TSC Ventilation System in Section 9.4.6.

Adds new accident range channels for PRMs 1, 2, and 6 per NUREG-0737 to Section 11.5.

Revises description of potential cross contamination in Section 11.2.3.2.2.

Revises description of preparation and analysis of weekly oily water separator composite sample in Section 11.2.3.2.2.

Eliminates description of sampling the sewage plant effluent or sludge in Section 11.2.3.2.2.

Deletes description of semiannual sampling of stator cooling water system in Section 11.2.3.2.2.

Corrects system name in Section 11.2.3.2.2 to Turbine Building bearing cooling water system from Turbine Building cooling water system.

Changes Figure 11.2-10 to show as-built conditions of reactor cavity cump discharge line.

Modifies Table 11.5-2 to include reference to PGE-1021.

Revises the description of the operating modes for the continu-ous gas monitoring systems in Section 11.5.2.2.

Revises Figure 11.5-1 to reflect new PRMs 1, 2, and 6 and new ARMS 15 through 25.

Adds Table 12.3-6 describing the locations of ARMS.

Corrects errors on Figures 12.3-3 through 12.3-7 which omitted ARM numbers and some ARM locations.

Trojan Nuclear Plant Mr. E. J. Butcher Docket 50-344 July 1, 1985 License NPF-1 Page 6 of 6 Revises Table 12.3-4 to clarify that ARMS 15A & B do not have local alarms.

Revises Table 15.8-1 to correct the Reactor Coolant System volume and make it consistent with Technical Specification 5.4.2.

Revises Sections 15.4.8.1.1 and 15.4.8.2.2 to indicate that no credit is taken for the positive rate trip in the rod ejection analyses.

Adds description of an alternate methodology used to calculate gamma and beta whole body doses to Section 15.0.11.2.

Deletes Figures 15.7-2 and 15.7-3. These figures showed dose vs distance for the fuel handling accident. Figure 15.7-3 did not reflect revisions to the thyroid dose calculation, and both figures are redundant, since the dose results are presented in Section 15.7.4.2.1.2.

BDW/BLK/3ml 0952G17.685