ML20202D939
| ML20202D939 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 07/01/1986 |
| From: | Withers B PORTLAND GENERAL ELECTRIC CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20202D943 | List: |
| References | |
| NUDOCS 8607140251 | |
| Download: ML20202D939 (6) | |
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Bart D Withers Vce Presdcyt July 1, 1986 Trojan Nuclear Plant Docket 50-344 License NPP-1 Director of Nuclear Reactor Regulation ATTN:
Mr. Steven A. Varga Director, PWR-A Project Directorate No. 3 U. S. Nuclear Regulatory Commission Washington DC 20555
Dear Sir:
TROJAN NUCLEAR PLANT Updated Final Safety Analysis Report. Amendment 4 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 4 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) changes made in the facility or procedures as described in the Updated FSAR submitted on July 20, 1982 and revised by Amendments 1 through 3; (b) safety evaluations performed by PGE, either in support of requested license cmendments or in support of conclusions that i
changes did not involve an unreviewed safety question; and (c) analyses of new safety issues performed by or on behalf of PGE 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 4 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 4 (July 1986)".
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Pornimid h hCorrpar1y Trojan Nuclear Plant Mr. S. A Varga Docket 50-344 July 1, 1986 License NPF-1 Page 2 ci 2 The attachment identifies the changes due to analyses submitted to the Comission or prepared pursuant to Commission requirements and the changes made under provisions of 10 CFR 50.59.
Other major sources of amendment information are also identified.
Because our schedule for submitting the annual FSAR Update coincides with numerous changes occurring to the design and analysis of the control room emergency ventilation system (CB-1), this amendment includes a description of these CB-1 changes to the extent possible.
Further changes will be described in a subsequent amendment, if necessary, by September 30, 1986.
Sincerely, n_-
3 Bart D. Withers Vice President Nuclear Attachment 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 1st day of July 1986.
L otary Public of Oc/gon My Commission Expires:
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Trojan Nuclear Plant Mr. S. A. Varga Docket 50-344 July 1, 1986 License NPF-1 Page 1 of.4 UPDATED FINAL SAFETY ANALYSIS REPORT IDENTIFICATION OF AMENDMENT 4 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 involve an unreviewed safety question.
1.
Plant Design Change 76-561 modified the hot machine shop and decontamination room facilities to expand the area available for decontamination. Section 12.5.2 was revised to describe this change.
2.
Plant Design Change 80-069 installed a new circulating water acid injection system. Section 10.4.6 was revised to describe this change.
3.
Plant Design Change 82-050 provided pressure transmitters and pump interlock circuitry for each CVCS hold-up tank to prevent tank collapse. Section 9.3.4.2.5 was revised to describe this change.
4.
Plant Design Change 82-055 modified the pressurizer safety and relief valves and pipe supports, and installed water slug diversion devices in the relief lines to remove the loop-seal fluid upon lifting of the relie! valve (s).
Section 5.4.11 was revised to describe this change.
5.
Plant Design Change 84-090 provided decouple switches for se-lected circuits to ensure these circuits are available for safe shutdown in the event of a fire. Section 8.3 was revised to describe this change.
6.
Plant Design Change 83-042 provided a shunt trip device for the reactor trip breakers. Section 7.2 was revised to describe this change.
7.
Plant Design Change 83-019 modified the isolation signals for the reactor coolant pump CCW valves. Section 7.3 and 9.2.2 were revised to describe this change.
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Trojan Nuclear Plant Mr. S. A. Varga Docket 50-344 July 1, 1986 License NPF-1 Page 2 of 4 8.
Plant Design Changes 83-03 and 84-080 replaced the tubes in selected feedwater heaters. Section 10.4 was revised to describe this change.
9.
Plant Design Change 81-064 provided additional blowdown flow instruments. Section 10.4.8 was revised to describe this change.
10.
Plant Design Change 86-021 relocated the control room emergency ventilation system outside air intake. Section 6.4 was revised to describe this change.
B.
Licensing Document Change Requests (LDCRs) - Licensing documents consist 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 following LDCRs were evaluated, and it was determined that their changes do not involve a change to the operating License, Technical Specifications, or an unreviewed safety or environmental question.
1.
LDCR 84-20 revised the Service Water System flow through the CCW heat exchanger and modified other flow requirements.
Sec-tions 6.3 and 9.2 were revised to include this change.
2.
LDCR 85-11 changed the meteorological instruments used to determine atmospheric stability.
Section 2.3 was revised to incorporate this change.
3.
LDCR 86-04 modified the exchange frequency of TLDs.
Section 12.5 was revised to include this change.
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 following license amendments is included in Amendment 4 to the Updated FSAR.
1.
Operating License Amendment No. 88 allowed expansion of the spent fuel pool storage capacity. Section 9.1 was revised to describe this change.
2.
Operating License Amendment No. 108 addressed organizational changes. Section 13.1 was revised to show this change.
D.
PGE to NRC Correspondence - This correspondence includes analyses and information submitted to the NRC or prepared per NRC requirements.
The following correspondence affects the Updated FSAR and was incorporated in Amendment 4.
Trojan Nuclear Plant Mr. S. A. Varga Docket 50-344 July 1, 1986 License NPF-1 Page 3 of 4
't 1.
PGE (B. D. Withers) to NRC (J. R. Miller) letter dated March 29, 1985 regarding electrical separation criteria. As a result of this letter, Section 8.3.1 was revised.
2.
LER 86-02, dated March 18, 1986 regarding control room emergency ventilation system. As a result of this letter, Sections 6.4, 9.4.1, 12.3 and 15.6.5 were 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, but not limited to the following:
Clarifies the comparison of Trojan Quality Group Classification with ANSI N18.2 in Section 3.2.
I Deletes description in Section 3.8.1.1.4.4 of airlock door seal test pressure at 69 psi, since 10 psig is the correct value per Technical Specification 4.6.1.3.
Revises the list of active valves in Table 3.9-25 to be consistent with the inservice test program.
Revises the description of the hydrogen vent system in Sec-tions 3.1, 3.2, 3.7 and 6.2.5.
Adds a description in Section 6.2 of leak testing for those Containment penetrations equipped with expansion bellows.
l Expands the description in Section 6.2.2.1 of the Containment spray switchover sequence to indicate that valve MO-2052A&B are l
normally tagged-out.
Expands the description of the RHR pump curves in Sec-tion 6.3.2.2.5.
3 Expands the ECCS single-failure analysis in Table 6.3-14.
I Adds a description in Section 7.3 of containment isolation Phase B.
Deletes text and figures from Section 8.3 associated with fire protection. The fire protection program is described in PCE-1012.
Corrects the shaft material for the spent fuel pool cooling pumps 4
l purification pump, and skimmer pump in Tables 9.1-3 through 9.1-5.
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s Trojan Nuclear Plant Mr. S. A. Varga Docket 50-344 July 1, 1986 License NPF-1 Page 4 of 4 Corrects the description of saiple piping design in Sec-tion 9.3.2.1.
Corrects the design basis humidity in Section 9.4.
Expands the description in Section 9.2 on PWST level control.
Revises the description 0,f Plant communications in Section 9.5.2.
Revises level setpoints for the dirty waste drain tank in Table 11.2-10.
Corrects the shaft material for selected radwaste treatrant system pumps in Tables 11.2-2 and 11.2-8.
Adds a description to Section 11.3 of releases from the main steam safety and relief valves.
Corrects the liquid level indication for the waste gas surge tank in Figure 11.3-1.
Corrects the summary of liquid sampling in Table 11.5-3 to be consistent with the Technical Specifications.
Revises the description of emergency and functional restoration instructions, and provides a description of emergency contingency actions and emergency fire procedures in Section 13.5.
Revises the number of full-time employees and associated listing of work groups in Section 13.1.2.1.
Expands the listing of Plant procedures in Section 13.5.
Corrects the description of temporary procedures in Sec-tion 13.5.15.
Updates the human factors engineering description in Chapter 18.
BLK/djh 0965W.0686