ML20214Q335
| ML20214Q335 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/01/1987 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20214Q338 | List: |
| References | |
| NLR-N87091, NUDOCS 8706040346 | |
| Download: ML20214Q335 (8) | |
Text
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Public Cervice Electric and Gas company Corbin A. McNeill, Jr.
Pubhc Seivice Electric and Gas Company P.O. Box 236, Hancocks Bridge. NJ 08038 609 339-4800 senor vice President -
Nuclear June 1 1987 NLR-N89091 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
REQUEST FOR AMENDMENT FACILITY OPERATING LICENSE NPF-57 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 In accordance with the requirements of 10CFR50.90, Public j
Service 81ectric and Gas Company (PSE&G) hereby transmits i
an emergency request for amendment of Facility Operating License NPF-57 for Hope Creek Generating Station (HCGS).
In accordance l
with the requirements of 10CFR170.21, a check in the amount of
$150.00 will be forwarded as soon as possible.
In accordance with the requirements of 10CFR50.91(b)(1), a copy of this request has been sent to the State of New Jersey as indicated below.
This amendment request revises Technical Specification Table 3.3.7.5-1, Accident Monitoring Instrumentation, for the Safety / Relief Valve Position Indicators (see Attachment 2).
This change permits PSE&G to avert an unnecessary plant shutdown as a result of an inoperable acoustic monitor for Safety / Relief Valve # F013H. contains further discussion and justification for these proposed revisions including a justification of the emergency circumstances.
PSE&G respectfully requests your immediate attention and issuance of an emergency amendment by June 4, 1987.
This submittal includes one (1) signed original, including affidavit, and thirty-seven (37) copies pursuant to 10CFR50.4(b)(2)(ii).
Should you have any questions on the subject transmittal, please do not hesitate to contact us.
Sincerely,
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Affidavit Attachments (2) g\\g 8706040346 870601 PDR ADOCK 05000354 P
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June 1, 1987 C
Mr. G. W. Rivenbark USNRC Licensing Project Manager Mr. R. W.
Borchardt USNRC Senior Resident Inspector Mr.
D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 i
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Re f:
HCGS LCR 87-09 STATE OF NEW JERSEY
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)
SS.
COUNTY OF SALEM
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Steven E. Miltenberger, being duly sworn according to law deposes and says:
I am Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated June 1,
- 1987, concerning Hope Creek Generating Station Emergency License Change Request 87-09, are true to the best of my knowledge, information and belief, b
/
Subscribp and Swor to before me this
/
day of 1987
/
N> J sacuskmeem
. -Notary Public of New Jersey g
ggg My Commission expires on w-
F.
ATTACIIMENT 1 l
I
PROPOSED EMERGENCY CHANGE TO LCR 87-09 TECHNICAL SPECIFICATIONS HOPE CREEK GENERATING STATION DOCKET NO. 50-354 I.
DESCRIPTION OF CHANGE ACTION 8 0(a) for Technical Specification Table 3.3.7.5-1, Accident Monitoring Instrumentation, Instrument No.
9, Safety / Relief Valve Position Indicators, requires a plant shutdown if an inoperable indicator channel is not restored to OPERABLE status within 7 days.
The requested emergency change would add a footnote (c) to Instrument No. 9 of the subject Table to permit the Acoustic Monitor Position Indicator for Safety / Relief Valve (SRV)
- FOl3H to remain inoperable until September 21, 1987 without applying the shutdown requirement of ACTION 80(a).
II.
REASON FOR CHANGE The proposed change is required to prevent an unneccesary plant shutdown due to the f ailure of only one of several means of determining the position of one of the fourteen Safety / Relief Valves.
III. JUSTIFICATION OF EMERGENCY CIRCUMSTANCES On May 28, 1987 at 1845 hours0.0214 days <br />0.513 hours <br />0.00305 weeks <br />7.020225e-4 months <br />, Hope Creek Generating Station declared the Acoustic Monitor Channel for the FOl3H SRV inoperable due to an upward shif t in the baseline acoustical output and significantly larger oscillations in the signal.
A thorough review of other plant parameters indicated that the associated SRV had not changed position and was not j
leaking through.
l System troubleshooting disclosed that the source of the problem is at the transmitter, access to, and repairs of which will require a plant cooldown and drywell entry.
i Without the possibility of restoring the channel to OPERABLE status while the plant is at power and in the absence of formal NRC relief from the requirements of ACTION 80(a) for Table 3.3.7.5-1, a plant shutdown must commence at 1845 hours0.0214 days <br />0.513 hours <br />0.00305 weeks <br />7.020225e-4 months <br /> on Thursday, June 4, 1987.
Since (i) PSE&G has exhausted all immediately available means to repair the subject acoustic monitor, (ii) further efforts to troubleshoot the instrument are restricted by the physical location of the transmitter, and (iii) the Technical Specification change required to temporarily eliminate the requirement to shutdown the plant must be reviewed, approved and issued by the NRC prior to 1845 hours0.0214 days <br />0.513 hours <br />0.00305 weeks <br />7.020225e-4 months <br /> on June 4, 1987, this request meets the criteria specified in 10CFR50.91(a) (5) f or emergency situations.
f.
. LCR 87-09 IV.
SCHEDULE FOR ATTAINING COMPLIANCE Hope Creek Generating Station is currently in compliance with the requirements of Facility Operating License NPF-57 and, absent Emergency Technical Specification Relief, will be required to commence a plant shutdown on June 4, 1987 at 1845 hours0.0214 days <br />0.513 hours <br />0.00305 weeks <br />7.020225e-4 months <br /> in order to remain in compliance.
The proposed change would permit continued plant operation beyond the above time limit, while maintaining compliance, until September 21, 1987.
This date corresponds to the currently projected start of a Fall outage which has been scheduled to complete required surveillances while minimizing the impact on the system interconnection during peak Summer electrical demand.
Necessary maintenance to return the FOl3H SRV Acoustic Monitor to OPERABLE status will be accomplished during this outage.
V.
SIGNIFICANT HAZARDS CONSIDERATION EVALUATION This change does not involve a significant increase in the probability or consequences of any previously evaluated accident.
FSAR Section 15.1.4 provides the analysis of an inadvertent opening of a main steam safety / relief valve.
This analysis assumes either a malfunction of the valve or an operator-initiated opening.
Since the proposed change affects only the operability of the 3RV position indication, the capability of the SRV, itself, to perform its intended function is not impaired.
The loss of acoustic monitoring indication does not prevent accurate determination of the position of its associated SRV.
The position of the FOl3H SRV can be determined by its relief tailpipe temperature monitor, which is OPERABLE, and by several other methods making use of operable plant parameters which include: (1) changes in main steam flow to the turbine, (ii) changes in gross generator (electrical) output, (iii) changes in suppression pool temperature as monitored by eight temperature elements spaced around the suppression chamber, and (iv) observation of perturbations in suppression pool level indication.
This change does not create the possibility for a new or dif ferent kind of accident f rom any that has been previously evaluated.
The proposed change would allow the acoustic monitor to remain inoperable until the specified repair date. There is no change in installed plant equipment or procedures and, as discussed above, there would still be adequate means for determining the associated SRV position with the acoustic monitor inoperable.
Since the acoustic monitor has no active function and its inoperability removes only one of several informational inputs to the control operators regarding SRV position, there is no new accident potential created.
f.-. LCR 87-09 V.
SIGNIFICANT HAZARDS CONSIDERATION EVALUATION (CONT'D)
The proposed change does not involve any significant reduction in any margin of safety.
Although the change would allow operation beyond the present requirements of ACTION 80(a) with one acoustic monitor channel inoperable for more than 7 days, there are other adequate means of determining the position of the FO13H SRV as described in the first paragraph of this SHC Evaluation.
Based on the above, PSE&G has determined that this proposed change would not involve a significant hazards consideration.
VI.
ENVIRONMENTAL IMPACT APPRAISAL As discussed in Paragraph V above, the operation of the plant with the proposed change in place does not affect the ability of the plant's physical barriers to limit or control a release to the environment following an accident.
The accident analysis considered would result in a discharge of normal coolant activity to the suppression chamber via SRV operation, but, because this activity is contained in the primary containment, there are no exposures to operating personnel or the general public.
The transient under consideration (inadvertent opening of a main steam line safety / relief valve) does not result in an uncontrolled release to the environment.
Since the accident analysis bounde any consequences associated with the proposed change, it will not result in a significant environmental impact nor does it change any previous environmental impacts for the Hope Creek Generating Station.
As a result, the proposed change meets the requirements f or categorical oxclusion under 10CFR51.22.
VII.
INTERIM COMPENSATORY MEASURES Since the station is currently in compliance and expects to remain so, and, as discussed in Paragraph V above, additional methods of verifying SRV position are available to the operators, no interim compensatory measures are necessary.
VIII. NOTIFICATION OF STATE PERSONNEL A copy of this proposed change is being provided to the Bureau of Nuclear Engineering, Department of Environmental Protection for the State of New Jersey.
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ATTACHMENT 2
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