ML20235C546
| ML20235C546 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/30/1987 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NLR-N87122, NUDOCS 8707090457 | |
| Download: ML20235C546 (5) | |
Text
_ _ _ _ - _ _ _ _ _ _
e Pubbe Service Electric and Gas Company Corbin A. McNeill, Jr.
Public Service Electric and Gas Company P.O. Box 236, Hancocks Bndge, NJ 08038 609 339-4800 Senior Vice President -
l N xlear June 30, 1987 NLR-N87122 j
United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
SUPPLEMENTAL INFORMATION - REQUEST FOR AMENDMENT FACILITY OPERATING LICENSE NPF-57 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 Public Service Electric and Gas Company (PSE&G) hereby provides supplemental information in support of the request for amendment submitted on May 22, 1987 (NLR-N87091) as requested by the NRC in a phone call dated June 18, 1987.
The referenced request revised Technical Specification Tables 2.2.1-1, 3.3.2-1 and 3.3.2-2, for the Main Steam Line Radiation - High High full power radiation background levels and associated setpoints, and would permit Hope Creek Generating Station (HCGS) to test the feasibility of a Hydrogen Water Chemistry system to mitigate intergranular stress corrosion cracking (IGSCC) of stainless steel recirculation piping.
Attachment I contains the requested supplemental information regarding testing guidelines, shielding, schedule and the inter-relationship of hydrogen to any onsite gaseous chlorine.
This information provides further details regarding the planned test and does not alter the conclusions reached pursuant to 10CFR50.92 previously submitted.
Should you have any questions, please do not hesitate to contact us.
Sincerely, A
t Attachment bk A
D h4 O
O o
Document Control Desk 2
6-30-87 C
Mr. G. W. Rivenbark USNRC Licensing Project Manager Mr.
R. W. Borchardt USNRC Senior Resident Inspector Mr.
W. T.
Russell, Administrator USNRC Region I Mr.
D. M. Scott, Chief Bureau of Nuclear Engineering DepartmentHof Environmental Protection 380 Scotch Road Trenton, NJ 08628
)
{
l
ATTACHMENT 1 The following supplemental information is being provided to respond to verbal questions regarding details onLthe hydrogen water chemistry test.
1.
The referenced.EPRI report, " Guidelines for Permanent BWR Hydrogen Water Chemistry Installations" (NP-4500-SR-LD) is dated March 1986 and forms the basis for many HCGS test features.
However, these EPRI guidelines have been updated in response to NRC questions and reissued in January 1987.
Will.HCGS follow these revised guidelines, specifically regarding tube truck separation distances?
RESPONSE
PSE&G has-recently. awarded General Electric (GE) the contract for conducting the HCGS Hydrogen Water Chemistry (HWC)
Pre-Implementation Mini-Test.
As a result of GE's extensive experience in conducting similar tests at other nuclear facilities, HCGS will utilize many GE recommendations when developing and conducting the HWC test.
In addition, the BWR Owners Group for IGSCC Research was' involved in the development fof,the referenced'EPRI guidelines and currently PSE&G has been informed that the January 1987 EPRI report is only a draft report undergoing NRC review and comment.
-Regardless, PSE&G will comply with the latest guidelines lavailable from EPRI and GE.
Although the EPRI guidelines are for permanent HWC systems, PSE&G will follow the separation distance for tube trucks specified in the draft January 1987 rather than those required by NFPA Code No.
50A.
PSE&G will utilize one hydrogen tube trailer containing approximately 130,000 SCF although only 100,000 SCF are expected to be=used, and one oxygen tube trailer containing 1/4 to 1/2 capacity'of the hydrogen tube trailer.
2.
Based on the expected radiation background level increases, will HCGS require additional or temporary shielding to protect station personnel and the public from this increase?
RESPONSE
PSE&G has reviewed HWC test results from other domestic boiling water reactors (BWRs) which indicate a wide variability in main steam line radiation increase ranging from e low of 1.5 to a high of a five-fold increase due to various equipment and piping arrangements, steam activity inventory and distance and origination of key facilities.
The two areas of concern associated with this activity increase are (1) the increase in in-plant occupational radiation exposure, and (2) the potential
. increase in site boundary dose rates.
Rather than attempting to quantify the expected increase at HCGS and to identify the location and amount of shielding within the station, PSE&G will utilize a combination of administrative controls, test scheduling i
J and monitoring to reduce exposures consistent with the practices utilized at other BWRs which have performed HWC tests.
1
i With regard to in-plant exposures, the areas most impacted are expected to be the turbine building and the environs outside the radiologically controlled area (RCA) but within the plant, i.e.,
the administrative areas adjacent to the turbine building and other onsite areas.
Some key locations may require a radiation status change from radiation area to high radiation area.
During the HWC test, extensive radiation surveys will be made in order to identify key locations and areas, and if required, access to these areas will be controlled and limited to the maximum extent possible.
Key areas will also be identified from experiences at other BWRs which have performed HWC tests. Temporary test monitoring and sampling equipment which requires personnel attention will be located in areas where the projected dose increase will be minimal.
In addition, in order to further minimize personnel exposure, the HWC test will be performed on a weekend and/or during swing shifts.
Other than activities required by or in support of the HWC test, access to the turbine building for general maintenance will not be permitted.
If emergency maintenance or access for other reasons is necessary, the HWC test will be terminated.
Due to the 7.3 second half life of N-16, radiation levels will return to pre-HWC test conditions within minutes of the hydrogen shutoff.
Although the offsite dose is expected to increase slightly from increased turbine shine, due to the short duration of the entire test, the 40CFR190 site boundary limit of 25 nrem/ year will not be exceeded.
Offsite and perimeter radiation surveys will typically be performed during each planned step increase in hydrogen injection.
Additional thermoluminescent devices (TLD) will be placed on and offsite to further document exposures.
These measures will be impleme.nted for the duration of the test.
The conduct of the test and radiological surveys during the test will insure occupational exposure is kept as low as reasonably achievable (ALARA).
One of the major goals of the HWC is to determine the radiological impact of HWC and to utilize the results in deciding whether a HWC system should be permanently installed at HCGS.
3.
What is the schedule for conducting the HWC test?
RESFONSE Currently, PSE&G is planning on conducting the HWC test in late August 987 assuming the requested license amendment is issued by the NRC prior to this time frame.
The decision to test at this time is based upon several PSE&G outages - HCGS in late September for Technical Specification and Inservice Inspection (ISI) surveillance and Salem Generating Station (SGS) Unit No. I for its seventh refueling outage in October-November 1987.
Testing prior to these time frames minimizes the amount of onsite personnel in keeping with the above discussed ALARA goals and maximizes HNC contractor support in order to successfully complete the HWC test and analyze the results obtained.
i 1
Although this schedule appears aggressive in light of the original May 22, 1987 request for amendment and this follow-up information, the proposed HWC test is similar to a variety of other BWR testing (including Hatch and Brunswick).
Additionally, PSE&G is implementing the test in accordance with standard j
industry guidelines and following the recommendations of the test 1
contractor, General Electric - the industry leader for this type of. test.
Consequently, PSE&G does not expect extensive NRC review comments which therefore per.dts the required public notice comment cycle to proceed smoothly and in a time frame supportive of the requested schedule.
4.
Does HCGS store gaseous chlorine onsite, and if so, what is the transportation and storage separation requirements regarding the hydrogen tube trailer.
FSAR Section 2.2.3 and Tables 2.2-4, 5 and 6 as well as Section 9.5.1.1.11 and Table 9.5-3 indicate that chlorine is not stored at HCGS and does not represent a transportation hazard past HCGS.
HCGS does utilize liquid sodium hypochlorite to control service water and circulating water biofouling but in this form the substance does not pose a hazard to the HWC test.
4