ML17139B838
| ML17139B838 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/28/1983 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML17139B837 | List: |
| References | |
| NUDOCS 8310120045 | |
| Download: ML17139B838 (10) | |
Text
SAFETY EVALUATION AHEPIDPI N
.16 r<
-14 SUSQUE NA S II1 EC R C 5 ATIOPJ, UNIT 1 Introduction The licensee in a letter dated January 31, 1983, proposed a change to License Condition 2.C.(6 ) of the operating license for Susquehanna Steam Electric Station, Unft 1 to incorporate Revision 2 to the Susquehanna Steam Electric Station Fire Protection Review Report into the approved report.
The proposed change would require the licensee to maintain and implement the provisions of the approved Fire Protection Review Report, as amended through Revision 2
dated November 1982.
The licensee in a letter dated PI~ 4, 1983, proposed changes to the Technical Specifications of the operating license for Susquehanna Steam Electric Station, Unit 1 which are as follows:
(a)
Correct typographical errors in Technical Specification Table 4.11.2.1.2-1 by deleting the asterisk on "Gaseous Release Type" and changing the a~plfcable footnote on "Principal Gamma Emitters" fn part c. from "b'o "g".
(b)
Change varfous references to systems of equipment fn Section 8.0, "Electrical Power Systems" as follows:
(1)
On page 3/4 8-8, change Device Tag No. "62X-20310" and "62X-20410" to "62X2-20310" and "62X2-20410" respectively, (2)
On page 3/4 8-20, change "1D622" to "1D662" fn Technical Specification 3.8.3.2.b.2.c),
(3)
On pages 3/4 8-24 through 3/4 8-26, add "+" footnote notation to the section a. title, "Ty e 2 IIolded Case Circuit Breakers".
On page 3/4 8-26, add "+"
ootnote to read, ac locat on no.
represents two breakers, A and B, fn series.",
(4)
On page 3/4 8-24, change "1B414A" in item 6 and "HYE821F016" fn item 14 to read "lV414A" and "HVB8211F016" respectively, (5)
On page 3/4 8-25, items 21, 22, and 24 through 28, change "IV417B" "IV414B", "IV415B", "IV416B" "IV411B" "IV413B" and "lV412B", respectively to "lY417B", "lV4148", UlV415B",
"lV416B", "lV411B", "1Y413B" and "lV412B", respectively, 83i0i20045 830928 PDR ADOCK 05000387 p
PDR OFFICE/
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OAIEP NRC FORM 3I8 IIO/80) NRCM 0240 OFFICIAL
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2 (6)
On page 3/4 8-26, change "IP402A" in item 33 to "1P402A",
change "1B263087" in item 37 to "18263081",
change "IP4023" in item 38 to "1P4023",
and change "IP403B" in item 40 to "1P403B" (7)
On page 3/4 8-27, change "T
e 3 Molded Core Circuit/Breakers" to "T e 3 Molded Case Circu t Brea ers n
tems t rougi 4,
c ange
(..
, and "IE440A 'espectively to "1E440C", "lE440D", "lE440B", and "1E440A" resp ctively, (8)
On page 3/4 8-31, change valve number UHV-Ell-1F0738" to "HV-Ell-1F073B" and change valve number "HB-E32-1F009" to "HV-E32-1F009",
(9)
On page 3/4 8-32, change valve number "HV-B31-1F032BB" to "HV-B31-F032B".
For valve numbers HV-B31-1F032A, HY-B31-1F032B, HY-031-1F031A and HY-B31-1F031B, change the System(s) Affected from "RHR" to "RX RECIRC".
(c)
Delete Technical Specification 4.7.2.b.
paragraph 1 and renumber paragraphs 2, 3, and 4 as paragraphs 1, 2, and 3 respectively.
(d)
Change the allowable value for the reactor vessel water level (high) trf~ setpoint in Technical Specification 3.3.9-2 from " < 54.0 inches" to '; 55.5 inches".
Evaluation By letter dated December 30, 1982, the licensee provided to the NRC staff, Revision 2 to the Susquehanna Steam Electric Station Fire Protection Review Report.
Changes in Revision 2 are primarily editorial in nature or reflect as-built conditions in the plant.
The NRC staff has reviewed Revision 2 to the Fire Protection Review Report and has determined the changes to be within and comply with current NRC and industry guidelines.
The NRC staff has also determined that the 'conclusfons reached in the Safety Evaluation Report and supplements on fire protection remain valid, and on that basis Revision 2 is acceptable.to the NRC staff for inclusion as part of the approved Fire Protection Review Report.
By letter dated January 31, 1983, the licensee requested a change to License Condition 2.C.(6) of Facility Operating License No. NPF-14 to read as follows:
"PP8L shall maintain in effect and fully implement all provisions of the approved Fire Protection Review Report.
In addition, PPEL shall maintain the fire protection program set for th in Appendix R to 10 CFR Part 50."
OFFICE)
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The NRC staff has reviewed this request and has determined that the speciftc revision to which the Fire Protection Review Report has been approved should be stated fn the license condition, as is the case of fts present format.
Thfs determination was discussed with and is acceptable to the licensee.
Therefore, License Condition 2.C.(6) is changed to read:
UPPSL shall maintain fn effect and fully implement all provisions of the approved Fire Protection Review Report, as amended through Revision 2
dated November 1982.
In addition, PPBL shall maintain the fire protection program set forth fn Appendix R to 10 CFR Part 50."
All changes described in paragraphs (a) and (b), above, as part of the licensee's submittal of Hay 4, 1983, are administrative fn nature to correct typographical errors with the exception of paragraphs (b)(l) and (b)(3).
The changes described fn paragraph (b)(1) above were requested as a result of field changes to tag numbers on two devfces.
The change to the Technical Specification fs to update the tag numbers to reflect the field change and maintain consistency.
The changes described in paragraph (b)(3) above are provided to clarify the fact that each circuit breaker location represents two breakers fn series, both of which are to be tested.
The NRC staff has reviewed the proposed changes described in paragraphs (a) and (b) above and determined the changes are acceptable on the basis that the changes are administrative fn nature to correct typographical
- errors, update nomenclature, or clarify current configurations.
The change described in paragraph (c) above, as part of the licensee's submittal of Hay 4, 1983, proposes to delete Technical Specification 4.7.2.b.l as a non-applicable item to the as-built condition of Susquehanna Steam Electric Station, Unit 1.
Specification 4.7.2.b.l addresses the control and minimization of leakage through the bypass damper, if provfded as part of the Control Room Emergency Outside Air Supply System.
The licensee stated the Susquehanna design does not and was never intended to include a bypass connection.
Tive NRC staff has reviewed the proposed change and finds ft acceptable on the basis that the change fs a result of editorial errors and should have been deleted in earlier reviews as a non-applicable item.
With the deletion of Specification 4.7.2.b.l, the NRC staff also finds ft acceptable to renumber sub-paragraphs 2, 3, and 4 under Specification 4.7.2.b to paragraphs 1, 2, and 3 respectively for continuity purposes.
The change described in paragraph (d) above, as part of the licensee's submittal of Hay 4, 1983, proposes to change the allo>Iable value for the reactor vessel water level (high) trip setpoint from
< 54.0 inches to
< 55.5 inches.
The licensee indicated in the PP&L submittal dated Hay 4, 1983, that a reanalysis of the "Feedwater Controller Failure to Haximum Demand" transient had been performed to determine the sensitivity of. the operating limit minimum critical power ratio (OL-HCPR) to a change in the allowable value for the reactor vessel OFFICE/
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4 water level (high) trip setpoint from
< 64.0 inches to
< 65.5 inches.
The results of the reanalysis indicate that the OL-tCPR remains the same.
Other licensing basis events do not take credit for the high water level trip.
The NRC staff has reviewed the licensee's proposed Technical Specification revision and the results of the supporting analysis and concludes that based on the (Ilg-hfCPR remaining the
- same, the proposed Technical Specification change is acceptable.
Environmental Consideration Me have determined that this amendment does not authorize a change in effluent types or total amount nor an increase in power level and will not result in any significant environmental impact.
Having made this determination, we have further concluded that this amendment involves action which is insignificant from the standpoint of environmental
- impact, and, pursuant to 10 CFR Section 51.5(d)(4), that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
Conclusion We have 'concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed
- manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Dated:
88 2 B f9N OFFICE)
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DATED:
Se tember 28 1983 Amendment No.
16 - Sus uehanna Steam Electric Station, Unit 1
NPF-14) j Document Control (50-387)+
NRC PDR Local PDR NSIC PRC LBA'2 File EHylton RLPerch
- ELJordan, DE(A:IE
- JHTaylor, DRP:IE
- Wagner, OELD HRDenton DEisenhut/RPurple DBrinkman, SSPB
- LJHarmon, IE (2),
JSauder WMiller IDinitiz
- WJones, gA TBarnhart (4)
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